Sample records for liquid waste treatment

  1. Membrane Treatment of Liquid Salt Bearing Radioactive Wastes

    SciTech Connect (OSTI)

    Dmitriev, S. A.; Adamovich, D. V.; Demkin, V. I.; Timofeev, E. M.

    2003-02-25T23:59:59.000Z

    The main fields of introduction and application of membrane methods for preliminary treatment and processing salt liquid radioactive waste (SLRW) can be nuclear power stations (NPP) and enterprises on atomic submarines (AS) utilization. Unlike the earlier developed technology for the liquid salt bearing radioactive waste decontamination and concentrating this report presents the new enhanced membrane technology for the liquid salt bearing radioactive waste processing based on the state-of-the-art membrane unit design, namely, the filtering units equipped with the metal-ceramic membranes of ''TruMem'' brand, as well as the electrodialysis and electroosmosis concentrators. Application of the above mentioned units in conjunction with the pulse pole changer will allow the marked increase of the radioactive waste concentrating factor and the significant reduction of the waste volume intended for conversion into monolith and disposal. Besides, the application of the electrodialysis units loaded with an ion exchange material at the end polishing stage of the radioactive waste decontamination process will allow the reagent-free radioactive waste treatment that meets the standards set for the release of the decontaminated liquid radioactive waste effluents into the natural reservoirs of fish-farming value.

  2. Decommissioning and Dismantling of Liquid Waste Storage and Liquid Waste Treatment Facility from Paldiski Nuclear Site, Estonia

    SciTech Connect (OSTI)

    Varvas, M. [AS ALARA, Leetse tee 21, Paldiski, 76806 (Estonia); Putnik, H. [Delegation of the European Commission to Russia, Kadashevskaja nab. 14/1 119017 Moscow (Russian Federation); Nirvin, B.; Pettersson, S. [SKB, Box 5864, Stockholm, SE-102 40 (Sweden); Johnsson, B. [Studsvik RadWaste, Nykoping, SE-611 82 (Sweden)

    2006-07-01T23:59:59.000Z

    The Paldiski Nuclear Facility in Estonia, with two nuclear reactors was owned by the Soviet Navy and was used for training the navy personnel to operate submarine nuclear reactors. After collapse of Soviet Union the Facility was shut down and handed over to the Estonian government in 1995. In co-operation with the Paldiski International Expert Reference Group (PIERG) decommission strategy was worked out and started to implement. Conditioning of solid and liquid operational waste and dismantling of contaminated installations and buildings were among the key issues of the Strategy. Most of the liquid waste volume, remained at the Facility, was processed in the frames of an Estonian-Finnish co-operation project using a mobile wastewater purification unit NURES (IVO International OY) and water was discharged prior to the site take-over. In 1999-2002 ca 120 m{sup 3} of semi-liquid tank sediments (a mixture of ion exchange resins, sand filters, evaporator and flocculation slurry), remained after treatment of liquid waste were solidified in steel containers and stored into interim storage. The project was carried out under the Swedish - Estonian co-operation program on radiation protection and nuclear safety. Contaminated installations in buildings, used for treatment and storage of liquid waste (Liquid Waste Treatment Facility and Liquid Waste Storage) were then dismantled and the buildings demolished in 2001-2004. (authors)

  3. Biological Information Document, Radioactive Liquid Waste Treatment Facility

    SciTech Connect (OSTI)

    Biggs, J.

    1995-12-31T23:59:59.000Z

    This document is intended to act as a baseline source material for risk assessments which can be used in Environmental Assessments and Environmental Impact Statements. The current Radioactive Liquid Waste Treatment Facility (RLWTF) does not meet current General Design Criteria for Non-reactor Nuclear Facilities and could be shut down affecting several DOE programs. This Biological Information Document summarizes various biological studies that have been conducted in the vicinity of new Proposed RLWTF site and an Alternative site. The Proposed site is located on Mesita del Buey, a mess top, and the Alternative site is located in Mortandad Canyon. The Proposed Site is devoid of overstory species due to previous disturbance and is dominated by a mixture of grasses, forbs, and scattered low-growing shrubs. Vegetation immediately adjacent to the site is a pinyon-juniper woodland. The Mortandad canyon bottom overstory is dominated by ponderosa pine, willow, and rush. The south-facing slope was dominated by ponderosa pine, mountain mahogany, oak, and muhly. The north-facing slope is dominated by Douglas fir, ponderosa pine, and oak. Studies on wildlife species are limited in the vicinity of the proposed project and further studies will be necessary to accurately identify wildlife populations and to what extent they utilize the project area. Some information is provided on invertebrates, amphibians and reptiles, and small mammals. Additional species information from other nearby locations is discussed in detail. Habitat requirements exist in the project area for one federally threatened wildlife species, the peregrine falcon, and one federal candidate species, the spotted bat. However, based on surveys outside of the project area but in similar habitats, these species are not expected to occur in either the Proposed or Alternative RLWTF sites. Habitat Evaluation Procedures were used to evaluate ecological functioning in the project area.

  4. Oak Ridge National Lebroatory Liquid&Gaseous Waste Treatment System Strategic Plan

    SciTech Connect (OSTI)

    Van Hoesen, S.D.

    2003-09-09T23:59:59.000Z

    Excellence in Laboratory operations is one of the three key goals of the Oak Ridge National Laboratory (ORNL) Agenda. That goal will be met through comprehensive upgrades of facilities and operational approaches over the next few years. Many of ORNL's physical facilities, including the liquid and gaseous waste collection and treatment systems, are quite old, and are reaching the end of their safe operating life. The condition of research facilities and supporting infrastructure, including the waste handling facilities, is a key environmental, safety and health (ES&H) concern. The existing infrastructure will add considerably to the overhead costs of research due to increased maintenance and operating costs as these facilities continue to age. The Liquid Gaseous Waste Treatment System (LGWTS) Reengineering Project is a UT-Battelle, LLC (UT-B) Operations Improvement Program (OIP) project that was undertaken to develop a plan for upgrading the ORNL liquid and gaseous waste systems to support ORNL's research mission.

  5. Treatment of Bottled Liquid Waste During Remediation of the Hanford 618-10 Burial Ground - 13001

    SciTech Connect (OSTI)

    Faulk, Darrin E.; Pearson, Chris M.; Vedder, Barry L.; Martin, David W. [Washington Closure Hanford, LLC, Richland, WA 99354 (United States)] [Washington Closure Hanford, LLC, Richland, WA 99354 (United States)

    2013-07-01T23:59:59.000Z

    A problematic waste form encountered during remediation of the Hanford Site 618-10 burial ground consists of bottled aqueous waste potentially contaminated with regulated metals. The liquid waste requires stabilization prior to landfill disposal. Prior remediation activities at other Hanford burial grounds resulted in a standard process for sampling and analyzing liquid waste using manual methods. Due to the highly dispersible characteristics of alpha contamination, and the potential for shock sensitive chemicals, a different method for bottle processing was needed for the 618-10 burial ground. Discussions with the United States Department of Energy (DOE) and United States Environmental Protection Agency (EPA) led to development of a modified approach. The modified approach involves treatment of liquid waste in bottles, up to one gallon per bottle, in a tray or box within the excavation of the remediation site. Bottles are placed in the box, covered with soil and fixative, crushed, and mixed with a Portland cement grout. The potential hazards of the liquid waste preclude sampling prior to treatment. Post treatment verification sampling is performed to demonstrate compliance with land disposal restrictions and disposal facility acceptance criteria. (authors)

  6. Treatment of liquid radioactive waste using combination of chemical processes with ultrafiltration

    SciTech Connect (OSTI)

    Zabrodsky, V.N.; Davidov, Y.P.; Toropov, I.G.; Glushko, A.S. [Academy of Sciences of Belarus, Minsk (Belarus). Inst. of Radioecological Problems; Efremenkov, V.M. [State Committee on Supervision of Industrial and Nuclear Safety, Minsk (Belarus)

    1993-12-31T23:59:59.000Z

    A combination of chemical processes and ultrafiltration was used for treatment of liquid radioactive wastes containing Cs, Sr, Pu by using large amounts of surfactants and complexing substances. The nature of carriers and conditions of complete separation of Cs and Sr are reported. The mechanisms of the processes are discussed.

  7. Process for preparing liquid wastes

    DOE Patents [OSTI]

    Oden, Laurance L. (Albany, OR); Turner, Paul C. (Albany, OR); O'Connor, William K. (Lebanon, OR); Hansen, Jeffrey S. (Corvallis, OR)

    1997-01-01T23:59:59.000Z

    A process for preparing radioactive and other hazardous liquid wastes for treatment by the method of vitrification or melting is provided for.

  8. Environmental assessment for liquid waste treatment at the Nevada Test Site, Nye County, Nevada

    SciTech Connect (OSTI)

    NONE

    1997-01-01T23:59:59.000Z

    This environmental assessment (EA) examines the potential impacts to the environment from treatment of low-level radioactive liquid and low-level mixed liquid and semi-solid wastes generated at the Nevada Test Site (NTS). The potential impacts of the proposed action and alternative actions are discussed herein in accordance with the National Environmental Policy Act (NEPA) of 1969, as amended in Title 42 U.S.C. (4321), and the US Department of Energy (DOE) policies and procedures set forth in Title 10 Code of Federal Regulations (CFR) Part 1021 and DOE Order 451.1, ``NEPA Compliance Program.`` The potential environmental impacts of the proposed action, construction and operation of a centralized liquid waste treatment facility, were addressed in the Final Environmental Impact Statement for the Nevada Test Site and Off-Site Locations in the State of Nevada. However, DOE is reevaluating the need for a centralized facility and is considering other alternative treatment options. This EA retains a centralized treatment facility as the proposed action but also considers other feasible alternatives.

  9. Treatment Options for Liquid Radioactive Waste. Factors Important for Selecting of Treatment Methods

    SciTech Connect (OSTI)

    Dziewinski, J.J.

    1998-09-28T23:59:59.000Z

    The cleanup of liquid streams contaminated with radionuclides is obtained by the selection or a combination of a number of physical and chemical separations, processes or unit operations. Among those are: Chemical treatment; Evaporation; Ion exchange and sorption; Physical separation; Electrodialysis; Osmosis; Electrocoagulation/electroflotation; Biotechnological processes; and Solvent extraction.

  10. The Mochovce final treatment center for liquid radioactive waste introduced to active trial operation

    SciTech Connect (OSTI)

    Krajc, T.; Stubna, M.; Kravarik, K.; Zatkulak, M. [VUJE Trnava, Inc. (Slovakia); Slezak, M.; Remias, V. [Javys - Jadrova a vyradovacia spolocnost, a.s. - Nuclear and Decommissioning Company, plc., Tomasikova 22, 821 02 Bratislava (Slovakia)

    2007-07-01T23:59:59.000Z

    The Final Treatment Centre (FTC) for Mochovce Nuclear Power Plant (NPP) have been designed for treatment and final conditioning of radioactive liquid and wet waste produced by named NPP equipped with Russian VVER-440 type of reactors. Treated wastes comprise radioactive concentrates, spent resin and sludge. VUJE Inc. as an experienced company in field of treatment of radioactive waste in Slovakia has been chosen as main contractor for technological part of FTC. During the realisation of project the future operator of Centre required the contractor to solve the treatment of wastes produced in the process of NPP A-1 decommissioning. On the basis of this requirement the project was modified in order to enable manipulations with waste products from A-1 NPP transported to Centre in steel drums. The initial project was prepared in 2003. The design and manufacture of main components were performed in 2004 and 2005. FTC civil works started in August 2004. Initial nonradioactive testing of the system parts were carried out from April to September 2006, then the tests of systems started with model concentrates and non-radioactive resins. After the processes evaluation the radioactive test performed from February 2007. A one-year trial operation of facility is planned for completion during 2007 and 2008. The company JAVYS, Inc. is responsible for radioactive waste and spent fuel treatment in the Slovak republic and will operate the FTC during trial operation and after its completion. This Company has also significant experience with operation of Jaslovske Bohunice Treatment Centre. The overall capacity of the FTC is 820 m{sup 3}/year of concentrates and 40 m{sup 3}/year of spent resin and sludge. Bituminization and cementation were provided as main technologies for treatment of these wastes. Treatment of concentrate is performed by bituminization on Thin Film Evaporator with rotating wiping blades. Spent resin and sludge are decanted, dried and mixed with bitumen in blade homogeniser. The bitumen product is discharged into 200 dm{sup 3} steel drums. Drums with bitumen product or drums originated from A-1 NPP are loaded into Fibre Reinforced Concrete containers (FRC) and grouted with cement. Cement grout is prepared from the mixture of cement, additive and radioactive over-concentrate. By formulating the cement grout with evaporator concentrates the maximum radioactivity is fixed in cement matrix and volume of final waste product is minimized. A batch mixer with rotating blades is used to produce the cement grout. The grouted FRC containers are stored in the expedition hall and after 28 days of curing are transported to final disposal. After the start of routine operation, the FTC provides treatment for all liquid and wet LLW produced from the operation of the Mochovce NPP. The final product of the FTC is a FRC loaded with bitumen product in drums and filled with radioactive cement product. This container meets all limits for final disposal in the National Radioactive Waste Repository at Mochovce. This paper introducing the main parts of FTC and describes the technological procedures including the basic technological parameters for both used technologies, their working capacity and the overall waste flow. The evaluation of experience gained in the phases of Centre construction and commissioning and partially trial operation as well is a part of this paper (Evaluation of completion works process and time schedule, the process of individual system parts testing, testing of systems using model media, radioactive testing and trial operation). (authors)

  11. EA-1115: Liquid Waste Treatment at the Nevada Test Site, Nye County, Nevada

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the proposal to treat low-level radioactive liquid and low-level mixed liquid and semi-solid wastes generated at the U.S. Department of Energy Nevada...

  12. The Radioactive Liquid Waste Treatment Facility Replacement Project at Los Alamos National Laboratory

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently AskedEnergyIssuesEnergy SolarRadioactive Liquid Waste Treatment Facility

  13. Hanford Facility dangerous waste permit application, liquid effluent retention facility and 200 area effluent treatment facility

    SciTech Connect (OSTI)

    Coenenberg, J.G.

    1997-08-15T23:59:59.000Z

    The Hanford Facility Dangerous Waste Permit Application is considered to 10 be a single application organized into a General Information Portion (document 11 number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the 12 Unit-Specific Portion is limited to Part B permit application documentation 13 submitted for individual, `operating` treatment, storage, and/or disposal 14 units, such as the Liquid Effluent Retention Facility and 200 Area Effluent 15 Treatment Facility (this document, DOE/RL-97-03). 16 17 Both the General Information and Unit-Specific portions of the Hanford 18 Facility Dangerous Waste Permit Application address the content of the Part B 19 permit application guidance prepared by the Washington State Department of 20 Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency 21 (40 Code of Federal Regulations 270), with additional information needs 22 defined by the Hazardous and Solid Waste Amendments and revisions of 23 Washington Administrative Code 173-303. For ease of reference, the Washington 24 State Department of Ecology alpha-numeric section identifiers from the permit 25 application guidance documentation (Ecology 1996) follow, in brackets, the 26 chapter headings and subheadings. A checklist indicating where information is 27 contained in the Liquid Effluent Retention Facility and 200 Area Effluent 28 Treatment Facility permit application documentation, in relation to the 29 Washington State Department of Ecology guidance, is located in the Contents 30 Section. 31 32 Documentation contained in the General Information Portion is broader in 33 nature and could be used by multiple treatment, storage, and/or disposal units 34 (e.g., the glossary provided in the General Information Portion). Wherever 35 appropriate, the Liquid Effluent Retention Facility and 200 Area Effluent 36 Treatment Facility permit application documentation makes cross-reference to 37 the General Information Portion, rather than duplicating text. 38 39 Information provided in this Liquid Effluent Retention Facility and 40 200 Area Effluent Treatment Facility permit application documentation is 41 current as of June 1, 1997.

  14. Final Treatment Center Project for Liquid and Wet Radioactive Waste in Slovakia

    SciTech Connect (OSTI)

    Kravarik, K.; Stubna, M.; Pekar, A.; Krajc, T.; Zatkulak, M.; Holicka, Z. [VUJE, Inc., Okruzna 5, 918 64 Trnava (Slovakia); Slezak, M. [SE - VYZ, 919 31 Jaslovske Bohunice (Slovakia)

    2006-07-01T23:59:59.000Z

    The Final Treatment Center (FTC) for Mochovce nuclear power plant (NPP) is designed for treatment and final conditioning of radioactive liquid and wet waste produced from plant operation. Mochovce NNP uses a Russian VVER-440 type reactor. Treated wastes comprise radioactive concentrates, spent resin and sludge. VUJE Inc. as an experienced company in field of treatment of radioactive waste in Slovakia has been chosen as main contractor for technological part of FTC. This paper describes the capacity, flow chart, overall waste flow and parameters of the main components in the FTC. The initial project was submitted for approval to the Slovak Electric plc. in 2003. The design and manufacture of main components were performed in 2004 and 2005. FTC construction work started early in 2004. Initial non-radioactive testing of the system is planned for summer 2006 and then radioactive tests are to be followed. A one-year trial operation of facility is planned for completion in 2007. SE - VYZ will be operates the FTC during trial operation and after its completion. SE - VYZ is subsidiary company of Slovak Electric plc. and it is responsible for treatment with radioactive waste and spent fuel in the Slovak republic. SE - VYZ has, besides of other significant experience with operation of Jaslovske Bohunice Treatment Centre. The overall capacity of the FTC is 870 m{sup 3}/year of concentrates and 40 m{sup 3}/year of spent resin and sludge. Bituminization and cementation were provided as main technologies for treatment of these wastes. Treatment of concentrate is performed by bituminization. Concentrate and bitumen are metered into a thin film evaporator with rotating wiping blades. Surplus water is evaporated and concentrate salts are embedded in bitumen. Bitumen product is discharged into 200 l steel drums. Spent resin and sludge are decanted, dried and mixed with bitumen. These mixtures are also discharged into 200 l steel drums. Drums are moved along bituminization line on a roller conveyor. After the drums cool, they are capped and removed from the conveyor and placed in a storage hall. Drums with bitumen product are loaded into Fiber Reinforced Concrete containers (FRC) and grouted with cement. Cement grout is prepared from mixture of cement, additive and radioactive concentrates. By formulating the cement grout with evaporator concentrates the maximum radioactivity is fixed in cement matrix and volume of final waste product is minimized. A batch mixer with rotating blades is used produce the cement grout. FRCs loaded with bitumen drums are placed on roller conveyor and moved along the cementation line. Grouted FRCs are stored in the expedition hall for 28 days of curing and then transported to final disposal. After placed in operation the FTC provides treatment for all liquid and wet LLW produced from the operation of the Mochovce NPP. The final product of the FTC is a FRC loaded with 7 drums of waste fixed in bitumen and the space between the drums is grouted with cement. This container meets all limits for final disposal in the National Radioactive Waste Repository at Mochovce. (authors)

  15. MUSHROOM WASTE MANAGEMENT PROJECT LIQUID WASTE MANAGEMENT

    E-Print Network [OSTI]

    of solid and liquid wastes generated at mushroom producing facilities. Environmental guidelines#12;MUSHROOM WASTE MANAGEMENT PROJECT LIQUID WASTE MANAGEMENT PHASE I: AUDIT OF CURRENT PRACTICE The Mushroom Waste Management Project (MWMP) was initiated by Environment Canada, the BC Ministry

  16. Development of US Navy Shipboard Systems for solid and liquid waste thermal treatment. Report for July 1995-April 1996

    SciTech Connect (OSTI)

    Gullet, B.K.

    1996-07-01T23:59:59.000Z

    The paper describes the U.S. Navy`s shipboard environmental challenges and a few of its research programs for meeting its needs for solid and liquid waste treatment. This objective is particularly important in environmentally sensitive areas, such as the Mediterranean Sea, where fleet deployment time is significant. Prohibitions on ocean dumping and anticipated requirements on effluent discharge quality have led the Navy to continue the research, development, and demonstration of shipboard systems to treat their unpreventable wastes. For solid, non-hazardous wastes, post-minimization efforts are geared toward long-term development of systems to thermally pyrolyze and oxidize the wastes into significantly reduced volume and weight.

  17. PLUTONIUM FINISHING PLANT (PFP) 241-Z LIQUID WASTE TREATMENT FACILITY DEACTIVATION AND DEMOLITION

    SciTech Connect (OSTI)

    JOHNSTON GA

    2008-01-15T23:59:59.000Z

    Fluor Hanford, Inc. (FH) is proud to submit the Plutonium Finishing Plant (PFP) 241-Z liquid Waste Treatment Facility Deactivation and Demolition (D&D) Project for consideration by the Project Management Institute as Project of the Year for 2008. The decommissioning of the 241-Z Facility presented numerous challenges, many of which were unique with in the Department of Energy (DOE) Complex. The majority of the project budget and schedule was allocated for cleaning out five below-grade tank vaults. These highly contaminated, confined spaces also presented significant industrial safety hazards that presented some of the most hazardous work environments on the Hanford Site. The 241-Z D&D Project encompassed diverse tasks: cleaning out and stabilizing five below-grade tank vaults (also called cells), manually size-reducing and removing over three tons of process piping from the vaults, permanently isolating service utilities, removing a large contaminated chemical supply tank, stabilizing and removing plutonium-contaminated ventilation ducts, demolishing three structures to grade, and installing an environmental barrier on the demolition site . All of this work was performed safely, on schedule, and under budget. During the deactivation phase of the project between November 2005 and February 2007, workers entered the highly contaminated confined-space tank vaults 428 times. Each entry (or 'dive') involved an average of three workers, thus equaling approximately 1,300 individual confined -space entries. Over the course of the entire deactivation and demolition period, there were no recordable injuries and only one minor reportable skin contamination. The 241-Z D&D Project was decommissioned under the provisions of the 'Hanford Federal Facility Agreement and Consent Order' (the Tri-Party Agreement or TPA), the 'Resource Conservation and Recovery Act of 1976' (RCRA), and the 'Comprehensive Environmental Response, Compensation, and Liability Act of 1980' (CERCLA). The project completed TPA Milestone M-083-032 to 'Complete those activities required by the 241-Z Treatment and Storage Unit's RCRA Closure Plan' four years and seven months ahead of this legally enforceable milestone. In addition, the project completed TPA Milestone M-083-042 to 'Complete transition and dismantlement of the 241-2 Waste Treatment Facility' four years and four months ahead of schedule. The project used an innovative approach in developing the project-specific RCRA closure plan to assure clear integration between the 241-Z RCRA closure activities and ongoing and future CERCLA actions at PFP. This approach provided a regulatory mechanism within the RCRA closure plan to place segments of the closure that were not practical to address at this time into future actions under CERCLA. Lessons learned from th is approach can be applied to other closure projects within the DOE Complex to control scope creep and mitigate risk. A paper on this topic, entitled 'Integration of the 241-Z Building D and D Under CERCLA with RCRA Closure at the PFP', was presented at the 2007 Waste Management Conference in Tucson, Arizona. In addition, techniques developed by the 241-Z D&D Project to control airborne contamination, clean the interior of the waste tanks, don and doff protective equipment, size-reduce plutonium-contaminated process piping, and mitigate thermal stress for the workers can be applied to other cleanup activities. The project-management team developed a strategy utilizing early characterization, targeted cleanup, and close coordination with PFP Criticality Engineering to significantly streamline the waste- handling costs associated with the project . The project schedule was structured to support an early transition to a criticality 'incredible' status for the 241-Z Facility. The cleanup work was sequenced and coordinated with project-specific criticality analysis to allow the fissile material waste being generated to be managed in a bulk fashion, instead of individual waste packages. This approach negated the need for real-time assay of individ

  18. Solvent extraction in the treatment of acidic high-level liquid waste : where do we stand?

    SciTech Connect (OSTI)

    Horwitz, E. P.; Schulz, W. W.

    1998-06-18T23:59:59.000Z

    During the last 15 years, a number of solvent extraction/recovery processes have been developed for the removal of the transuranic elements, {sup 90}Sr and {sup 137}Cs from acidic high-level liquid waste. These processes are based on the use of a variety of both acidic and neutral extractants. This chapter will present an overview and analysis of the various extractants and flowsheets developed to treat acidic high-level liquid waste streams. The advantages and disadvantages of each extractant along with comparisons of the individual systems are discussed.

  19. Waste Treatment Plant Overview

    Office of Environmental Management (EM)

    contracted Bechtel National, Inc., to design and build the world's largest radioactive waste treatment plant. The Waste Treatment and Immobilization Plant (WTP), also known as the...

  20. Transfer Lines to Connect Liquid Waste Facilities and Salt Waste...

    Office of Environmental Management (EM)

    Transfer Lines to Connect Liquid Waste Facilities and Salt Waste Processing Facility Transfer Lines to Connect Liquid Waste Facilities and Salt Waste Processing Facility October...

  1. New Standards in Liquid Waste Treatment at Fukushima Dai-ichi - 13134

    SciTech Connect (OSTI)

    Sylvester, Paul; Milner, Tim; Ruffing, Jennifer; Poole, Scott [EnergySolutions, 100 Center Point Circle, Suite 100, Center Point II, Columbia, SC 29210 (United States)] [EnergySolutions, 100 Center Point Circle, Suite 100, Center Point II, Columbia, SC 29210 (United States); Townson, Paul; Jensen, Jesse [EnergySolutions, 2345 Stevens Drive, Suite 240, Richland, WA 99354 (United States)] [EnergySolutions, 2345 Stevens Drive, Suite 240, Richland, WA 99354 (United States)

    2013-07-01T23:59:59.000Z

    The earthquake and tsunami on March 11, 2011 severely damaged the Fukushima Dai-ichi nuclear plant leading to the most severe nuclear incident since Chernobyl. Ongoing operations to cool the damaged reactors at the site have led to the generation of highly radioactive coolant water. This is currently mainly treated to remove Cs-137 and Cs-134 and passed through a reverse osmosis (RO) unit to reduce the salinity before being cycled back to the reactors. Because only the Cs isotopes are removed, the RO reject water still contains many radioactive isotopes and this has led to the accumulation of over 200,000 cubic meters (52 million gallons) of extremely contaminated water which is currently stored on site in tanks. EnergySolutions, in partnership with Toshiba, were contracted to develop a system to reduce 62 isotopes in this waste down to allowable levels. This was a significant technical challenge given the high background salt content of the wastewater, the variation in aqueous chemistry of the radioactive isotopes and the presence of non-active competing ions (e.g. Ca and Mg) which inhibit the removal of isotopes such as Sr-89 and Sr-90. Extensive testing was performed to design a suitable system that could meet the required decontamination goals. These tests were performed over a 6 month period at facilities available in the nearby Fukushima Dai-ni laboratory using actual waste samples. This data was then utilized to design a Multi Radioactive Nuclides Removal System (MRRS) for Fukushima which is a modified version of EnergySolutions' proprietary Advanced Liquid Processing System (ALPS)'. The stored tank waste is fed into a preliminary precipitation system where iron flocculation is performed to remove a number of isotopes, including Sb-125, Ru-106, Mn-54 and Co-60. The supernatant is then fed into a second precipitation tank where the pH is adjusted and the bulk of the Mg, Ca and Sr precipitated out as carbonates and hydroxides. After passing through a cross-flow ultrafiltration membrane, the permeate then goes through a total of 14 fixed ion exchange and adsorbent columns followed by a disposable polishing column to polish the residual isotopes down to allowable levels. At the end of the system, the effluent is filtered for a final time to removal any particulates that may have been picked up from the media columns and then stored prior to analysis. (authors)

  2. Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste

    E-Print Network [OSTI]

    Tsien, Roger Y.

    Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste Description Biohazard symbol Address: UCSD 9500 Gilman Drive La Jolla, CA 92093 (858) 534) and identity of liquid waste Biohazard symbol Address: UCSD 9500 Gilman Drive La Jolla, CA 92093 (858) 534

  3. Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste

    E-Print Network [OSTI]

    Tsien, Roger Y.

    2/2009 Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste Description Biohazard symbol Address: UCSD 200 West Arbor Dr. San Diego, CA 92103 (619 (9:1) OR Biohazard symbol (if untreated) and identity of liquid waste Biohazard symbol Address

  4. Development of low level liquid waste treatment systems: April-September 1981

    SciTech Connect (OSTI)

    Williams, M.K.; Colvin, C.M.; Bond, W.H.

    1982-03-05T23:59:59.000Z

    The pilot plant reverse osmosis system was demonstrated to be effective in removing large percentages of cobalt-60, iodine-125, and a mixture of cesium-137, cobalt-60, and iodine-125 from two types of aqueous streams. The effectiveness of three membrane porosities, 0, 50, and 97% salt rejection, were explored with each isotope. The 97% salt rejection membrane was the most effective in each experiment. Removals as high as 97.5% of the cobalt, 92.9% of the iodine and 95.1% of the combined isotopes were achieved. The effect of possibly interfering factors on the adsorbence of cobalt-60 and iodine-129 on selected ion exchange resins were investigated. The factors thought to affect cobalt-60 adsorption were (OH/sup -/), (NH/sub 4//sup +/), and (SO/sub 3//sup =/). None of the seven factors investigated had any effect on iodine-129 adsorption. Cesium-137 was removed from a 4600-gal aqueous waste containing a large amount of sodium hydroxide by treatment with sodium tetraphenyl boron. The cesium concentration of the supernatant portion was reduced from 570 to 4 counts/min/ml.

  5. Report on the flowsheet model for the electrochemical treatment of liquid radioactive wastes

    SciTech Connect (OSTI)

    Hobbs, D.T.

    1995-04-11T23:59:59.000Z

    The objective of this report is to describe the modeling and optimization procedure for the electrochemical removal of nitrates and nitrites from low level radioactive wastes. The simulation is carried out in SPEEDUP{trademark}, which is a state of the art flowsheet modeling package. The flowsheet model will provide a better understanding of the process and aid in the scale-up of the system. For example, the flowsheet model has shown that the electrochemical cell must be operated in batch mode to achieve 95% destruction. The present status of the flowsheet model is detailed in this report along with a systematic description of the batch optimization of the electrochemical cell. Results from two batch runs and one optimization run are also presented.

  6. Method for treating liquid wastes

    DOE Patents [OSTI]

    Katti, K.V.; Volkert, W.A.; Singh, P.; Ketring, A.R.

    1995-12-26T23:59:59.000Z

    The method of treating liquid waste in a media is accomplished by exposing the media to phosphinimines and sequestering {sup 99}Tc from the media by the phosphinimine (PN) functionalities. The system for treating the liquid waste in the media includes extraction of {sup 99}TcO{sub 4}{sup {minus}} from aqueous solutions into organic solvents or mixed organic/polar media, extraction of {sup 99}Tc from solutions on a solid matrix by using a container containing PN functionalities on solid matrices including an inlet and outlet for allowing flow of media through an immobilized phosphinimine ligand system contained within the container. Also, insoluble suspensions of phosphinimine functionalities on solid matrices in liquid solutions or present on supported liquid membranes (SLM) can be used to sequester {sup 99}Tc from those liquids. 6 figs.

  7. Method for treating liquid wastes

    DOE Patents [OSTI]

    Katti, Kattesh V. (Columbia, MO); Volkert, Wynn A. (Columbia, MO); Singh, Prahlad (Columbia, MO); Ketring, Alan R. (Columbia, MO)

    1995-01-01T23:59:59.000Z

    The method of treating liquid waste in a media is accomplished by exposing the media to phosphinimines and sequestering .sup.99 Tc from the media by the phosphinimine (PN) functionalities. The system for treating the liquid waste in the media includes extraction of .sup.99 TcO.sub.4.sup.- from aqueous solutions into organic solvents or mixed organic/polar media, extraction of .sup.99 Tc from solutions on a solid matrix by using a container containing PN functionalities on solid matrices including an inlet and outlet for allowing flow of media through an immobilized phosphinimine ligand system contained within the container. Also, insoluble suspensions of phosphinimine functionalities on solid matrices in liquid solutions or present on supported liquid membranes (SLM) can be used to sequester .sup.99 Tc from those liquids.

  8. Technology for Treatment of Liquid Radioactive Waste Generated during Uranium and Plutonium Chemical and Metallurgical Manufacturing in FSUE PO Mayak - 13616

    SciTech Connect (OSTI)

    Adamovich, D. [SUE MosSIA Radon, 2/14 7th Rostovsky lane, Moscow, 119121 (Russian Federation)] [SUE MosSIA Radon, 2/14 7th Rostovsky lane, Moscow, 119121 (Russian Federation); Batorshin, G.; Logunov, M.; Musalnikov, A. [FSUE 'PO Mayak', 31 av. Lenin, Ozyorsk, Chelyabinsk region, 456780 (Russian Federation)] [FSUE 'PO Mayak', 31 av. Lenin, Ozyorsk, Chelyabinsk region, 456780 (Russian Federation)

    2013-07-01T23:59:59.000Z

    Created technological scheme for treatment of liquid radioactive waste generated while uranium and plutonium chemical and metallurgical manufacturing consists of: - Liquid radioactive waste (LRW) purification from radionuclides and its transfer into category of manufacturing waste; - Concentration of suspensions containing alpha-nuclides and their further conversion to safe dry state (calcinate) and moving to long controlled storage. The following technologies are implemented in LRW treatment complex: - Settling and filtering technology for treatment of liquid intermediate-level waste (ILW) with volume about 1500m{sup 3}/year and alpha-activity from 10{sup 6} to 10{sup 8} Bq/dm{sup 3} - Membrane and sorption technology for processing of low-level waste (LLW) of radioactive drain waters with volume about 150 000 m{sup 3}/year and alpha-activity from 10{sup 3} to 10{sup 4} Bq/dm{sup 3}. Settling and filtering technology includes two stages of ILW immobilization accompanied with primary settling of radionuclides on transition metal hydroxides with the following flushing and drying of the pulp generated; secondary deep after settling of radionuclides on transition metal hydroxides with the following solid phase concentration by the method of tangential flow ultrafiltration. Besides, the installation capacity on permeate is not less than 3 m{sup 3}/h. Concentrates generated are sent to calcination on microwave drying (MW drying) unit. Membrane and sorption technology includes processing of averaged sewage flux by the method of tangential flow ultrafiltration with total capacity of installations on permeate not less than 18 m{sup 3}/h and sorption extraction of uranium from permeate on anionite. According to radionuclide contamination level purified solution refers to general industrial waste. Concentrates generated during suspension filtering are evaporated in rotary film evaporator (RFE) in order to remove excess water, thereafter they are dried on infrared heating facility. Solid concentrate produced is sent for long controlled storage. Complex of the procedures carried out makes it possible to solve problems on treatment of LRW generated while uranium and plutonium chemical and metallurgical manufacturing in Federal State Unitary Enterprise (FSUE) Mayak and cease its discharge into open water reservoirs. (authors)

  9. Hanford Tank Waste - Near Source Treatment of Low Activity Waste

    SciTech Connect (OSTI)

    Ramsey, William Gene

    2013-08-15T23:59:59.000Z

    Abstract only. Treatment and disposition of Hanford Site waste as currently planned consists of 100+ waste retrievals, waste delivery through up to 8+ miles of dedicated, in-ground piping, centralized mixing and blending operations- all leading to pre-treatment combination and separation processes followed by vitrification at the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The sequential nature of Tank Farm and WTP operations requires nominally 15-20 years of continuous operations before all waste can be retrieved from many Single Shell Tanks (SSTs). Also, the infrastructure necessary to mobilize and deliver the waste requires significant investment beyond that required for the WTP. Treating waste as closely as possible to individual tanks or groups- as allowed by the waste characteristics- is being investigated to determine the potential to 1) defer, reduce, and/or eliminate infrastructure requirements, and 2) significantly mitigate project risk by reducing the potential and impact of single point failures. The inventory of Hanford waste slated for processing and disposition as LAW is currently managed as high-level waste (HLW), i.e., the separation of fission products and other radionuclides has not commenced. A significant inventory of this waste (over 20M gallons) is in the form of precipitated saltcake maintained in single shell tanks, many of which are identified as potential leaking tanks. Retrieval and transport (as a liquid) must be staged within the waste feed delivery capability established by site infrastructure and WTP. Near Source treatment, if employed, would provide for the separation and stabilization processing necessary for waste located in remote farms (wherein most of the leaking tanks reside) significantly earlier than currently projected. Near Source treatment is intended to address the currently accepted site risk and also provides means to mitigate future issues likely to be faced over the coming decades. This paper describes the potential near source treatment and waste disposition options as well as the impact these options could have on reducing infrastructure requirements, project cost and mission schedule.

  10. Liquid and Gaseous Waste Operations Department Annual Operating Report, CY 1993

    SciTech Connect (OSTI)

    Maddox, J.J.; Scott, C.B.

    1994-02-01T23:59:59.000Z

    This report summarizes the activities of the waste management operations section of the liquid and gaseous waste operations department at ORNL for 1993. The process waste, liquid low-level waste, gaseous waste systems activities are reported, as well as the low-level waste solidification project. Upgrade activities is the various waste processing and treatment systems are summarized. A maintenance activity overview is provided, and program management, training, and other miscellaneous activities are covered.

  11. Newly Generated Liquid Waste Processing Alternatives Study, Volume 1

    SciTech Connect (OSTI)

    Landman, William Henry; Bates, Steven Odum; Bonnema, Bruce Edward; Palmer, Stanley Leland; Podgorney, Anna Kristine; Walsh, Stephanie

    2002-09-01T23:59:59.000Z

    This report identifies and evaluates three options for treating newly generated liquid waste at the Idaho Nuclear Technology and Engineering Center of the Idaho National Engineering and Environmental Laboratory. The three options are: (a) treat the waste using processing facilities designed for treating sodium-bearing waste, (b) treat the waste using subcontractor-supplied mobile systems, or (c) treat the waste using a special facility designed and constructed for that purpose. In studying these options, engineers concluded that the best approach is to store the newly generated liquid waste until a sodium-bearing waste treatment facility is available and then to co-process the stored inventory of the newly generated waste with the sodium-bearing waste. After the sodium-bearing waste facility completes its mission, two paths are available. The newly generated liquid waste could be treated using the subcontractor-supplied system or the sodium-bearing waste facility or a portion of it. The final decision depends on the design of the sodium-bearing waste treatment facility, which will be completed in coming years.

  12. Surrogate formulations for thermal treatment of low-level mixed waste, Part II: Selected mixed waste treatment project waste streams

    SciTech Connect (OSTI)

    Bostick, W.D.; Hoffmann, D.P.; Chiang, J.M.; Hermes, W.H.; Gibson, L.V. Jr.; Richmond, A.A. [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States)] [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States); Mayberry, J. [Science Applications International Corp., Idaho Falls, ID (United States)] [Science Applications International Corp., Idaho Falls, ID (United States); Frazier, G. [Univ. of Tennessee, Knoxville, TN (United States)] [Univ. of Tennessee, Knoxville, TN (United States)

    1994-01-01T23:59:59.000Z

    This report summarizes the formulation of surrogate waste packages, representing the major bulk constituent compositions for 12 waste stream classifications selected by the US DOE Mixed Waste Treatment Program. These waste groupings include: neutral aqueous wastes; aqueous halogenated organic liquids; ash; high organic content sludges; adsorbed aqueous and organic liquids; cement sludges, ashes, and solids; chloride; sulfate, and nitrate salts; organic matrix solids; heterogeneous debris; bulk combustibles; lab packs; and lead shapes. Insofar as possible, formulation of surrogate waste packages are referenced to authentic wastes in inventory within the DOE; however, the surrogate waste packages are intended to represent generic treatability group compositions. The intent is to specify a nonradiological synthetic mixture, with a minimal number of readily available components, that can be used to represent the significant challenges anticipated for treatment of the specified waste class. Performance testing and evaluation with use of a consistent series of surrogate wastes will provide a means for the initial assessment (and intercomparability) of candidate treatment technology applicability and performance. Originally the surrogate wastes were intended for use with emerging thermal treatment systems, but use may be extended to select nonthermal systems as well.

  13. Future radioactive liquid waste streams study

    SciTech Connect (OSTI)

    Rey, A.S.

    1993-11-01T23:59:59.000Z

    This study provides design planning information for the Radioactive Liquid Waste Treatment Facility (RLWTF). Predictions of estimated quantities of Radioactive Liquid Waste (RLW) and radioactivity levels of RLW to be generated are provided. This information will help assure that the new treatment facility is designed with the capacity to treat generated RLW during the years of operation. The proposed startup date for the RLWTF is estimated to be between 2002 and 2005, and the life span of the facility is estimated to be 40 years. The policies and requirements driving the replacement of the current RLW treatment facility are reviewed. Historical and current status of RLW generation at Los Alamos National Laboratory are provided. Laboratory Managers were interviewed to obtain their insights into future RLW activities at Los Alamos that might affect the amount of RLW generated at the Lab. Interviews, trends, and investigation data are analyzed and used to create scenarios. These scenarios form the basis for the predictions of future RLW generation and the level of RLW treatment capacity which will be needed at LANL.

  14. Ventilation System to Improve Savannah River Site's Liquid Waste...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Ventilation System to Improve Savannah River Site's Liquid Waste Operations Ventilation System to Improve Savannah River Site's Liquid Waste Operations August 28, 2014 - 12:00pm...

  15. Savannah River Site's Liquid Waste Operations Adds Multi-Functional...

    Office of Environmental Management (EM)

    Savannah River Site's Liquid Waste Operations Adds Multi-Functional Laboratory Savannah River Site's Liquid Waste Operations Adds Multi-Functional Laboratory January 28, 2015 -...

  16. Enterprise Assessments Operational Awareness Record, Waste Treatment...

    Broader source: Energy.gov (indexed) [DOE]

    system (LMH), the melter equipment support handling system (LSH), the radioactive solid waste handling system (RWH), and the radioactive liquid waste disposal system (RLD)....

  17. National Institutes of Health: Mixed waste minimization and treatment

    SciTech Connect (OSTI)

    NONE

    1995-08-01T23:59:59.000Z

    The Appalachian States Low-Level Radioactive Waste Commission requested the US Department of Energy`s National Low-Level Waste Management Program (NLLWMP) to assist the biomedical community in becoming more knowledgeable about its mixed waste streams, to help minimize the mixed waste stream generated by the biomedical community, and to identify applicable treatment technologies for these mixed waste streams. As the first step in the waste minimization process, liquid low-level radioactive mixed waste (LLMW) streams generated at the National Institutes of Health (NIH) were characterized and combined into similar process categories. This report identifies possible waste minimization and treatment approaches for the LLMW generated by the biomedical community identified in DOE/LLW-208. In development of the report, on site meetings were conducted with NIH personnel responsible for generating each category of waste identified as lacking disposal options. Based on the meetings and general waste minimization guidelines, potential waste minimization options were identified.

  18. ICPP radioactive liquid and calcine waste technologies evaluation. Interim report

    SciTech Connect (OSTI)

    Murphy, J.A.; Pincock, L.F.; Christiansen, I.N.

    1994-06-01T23:59:59.000Z

    The Department of Energy (DOE) has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage since 1951 and reprocessing since 1953. Until recently, the major activity of the ICPP has been the reprocessing of SNF to recover fissile uranium; however, changing world events have raised questions concerning the need to recover and recycle this material. In April 1992, DOE chose to discontinue reprocessing SNF for uranium recovery and shifted its focus toward the management and disposition of radioactive wastes accumulated through reprocessing activities. Currently, 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste) and 3,800 cubic meters (m{sup 3}) of calcine waste are in inventory at the ICPP. Legal drivers and agreements exist obligating the INEL to develop, demonstrate, and implement technologies for safe and environmentally sound treatment and interim storage of radioactive liquid and calcine waste. Candidate treatment processes and waste forms are being evaluated using the Technology Evaluation and Analysis Methodology (TEAM) Model. This process allows decision makers to (1) identify optimum radioactive waste treatment and disposal form alternatives; (2) assess tradeoffs between various optimization criteria; (3) identify uncertainties in performance parameters; and (4) focus development efforts on options that best satisfy stakeholder concerns. The Systems Analysis technology evaluation presented in this document supports the DOE in selecting the most effective radioactive liquid and calcine waste management plan to implement in compliance with established regulations, court orders, and agreements.

  19. Biohazardous Waste Disposal GuidelinesDescriptionStorage& LabelingTreatmentDisposal

    E-Print Network [OSTI]

    Wikswo, John

    Waste Sharps Waste Solid Lab Waste Liquid Waste Any of these devices if contaminated with biohazardousBiohazardous Waste Disposal GuidelinesDescriptionStorage& packaging LabelingTreatmentDisposal Mixed container. Container must be leakproof, ridgid, puncture resistant, clearly marked for biohazardous waste

  20. Independent Oversight Review, Waste Treatment and Immobilization...

    Energy Savers [EERE]

    Waste Treatment and Immobilization Plant Project - October 2010 October 2010 Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant...

  1. Independent Oversight Assessment, Waste Treatment and Immobilization...

    Office of Environmental Management (EM)

    Waste Treatment and Immobilization Plant - January 2012 Independent Oversight Assessment, Waste Treatment and Immobilization Plant - January 2012 January 2012 Assessment of the...

  2. Waste management system alternatives for treatment of wastes from spent fuel reprocessing

    SciTech Connect (OSTI)

    McKee, R.W.; Swanson, J.L.; Daling, P.M.; Clark, L.L.; Craig, R.A.; Nesbitt, J.F.; McCarthy, D.; Franklin, A.L.; Hazelton, R.F.; Lundgren, R.A.

    1986-09-01T23:59:59.000Z

    This study was performed to help identify a preferred TRU waste treatment alternative for reprocessing wastes with respect to waste form performance in a geologic repository, near-term waste management system risks, and minimum waste management system costs. The results were intended for use in developing TRU waste acceptance requirements that may be needed to meet regulatory requirements for disposal of TRU wastes in a geologic repository. The waste management system components included in this analysis are waste treatment and packaging, transportation, and disposal. The major features of the TRU waste treatment alternatives examined here include: (1) packaging (as-produced) without treatment (PWOT); (2) compaction of hulls and other compactable wastes; (3) incineration of combustibles with cementation of the ash plus compaction of hulls and filters; (4) melting of hulls and failed equipment plus incineration of combustibles with vitrification of the ash along with the HLW; (5a) decontamination of hulls and failed equipment to produce LLW plus incineration and incorporation of ash and other inert wastes into HLW glass; and (5b) variation of this fifth treatment alternative in which the incineration ash is incorporated into a separate TRU waste glass. The six alternative processing system concepts provide progressively increasing levels of TRU waste consolidation and TRU waste form integrity. Vitrification of HLW and intermediate-level liquid wastes (ILLW) was assumed in all cases.

  3. Treatment of mercury containing waste

    DOE Patents [OSTI]

    Kalb, Paul D. (Wading River, NY); Melamed, Dan (Gaithersburg, MD); Patel, Bhavesh R (Elmhurst, NY); Fuhrmann, Mark (Babylon, NY)

    2002-01-01T23:59:59.000Z

    A process is provided for the treatment of mercury containing waste in a single reaction vessel which includes a) stabilizing the waste with sulfur polymer cement under an inert atmosphere to form a resulting mixture and b) encapsulating the resulting mixture by heating the mixture to form a molten product and casting the molten product as a monolithic final waste form. Additional sulfur polymer cement can be added in the encapsulation step if needed, and a stabilizing additive can be added in the process to improve the leaching properties of the waste form.

  4. HUMAN MACHINE INTERFACE (HMI) EVALUATION OF ROOMS TA-50-1-60/60A AT THE RADIOACTIVE LIQUID WASTE TREATMENT FACILITY (RLWTF)

    SciTech Connect (OSTI)

    Gilmore, Walter E. [Los Alamos National Laboratory; Stender, Kerith K. [Los Alamos National Laboratory

    2012-08-29T23:59:59.000Z

    This effort addressed an evaluation of human machine interfaces (HMIs) in Room TA-50-1-60/60A of the Radioactive Liquid Waste Treatment Facility (RLWTF). The evaluation was performed in accordance with guidance outlined in DOE-STD-3009, DOE Standard Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, 2006 [DOE 2006]. Specifically, Chapter 13 of DOE 2006 highlights the 10 CFR 830, Nuclear Safety Management, 2012, [CFR 2012] and DOE G 421.1-2 [DOE 2001a] requirements as they relate to the human factors process and, in this case, the safety of the RLWTF. The RLWTF is a Hazard Category 3 facility and, consequently, does not have safety-class (SSCs). However, safety-significant SSCs are identified. The transuranic (TRU) wastewater tanks and associated piping are the only safety-significant SSCs in Rooms TA-50-1-60/60A [LANL 2010]. Hence, the human factors evaluation described herein is only applicable to this particular assemblage of tanks and piping.

  5. Sodium-Bearing Waste Treatment Alternatives Implementation Study

    SciTech Connect (OSTI)

    Charles M. Barnes; James B. Bosley; Clifford W. Olsen

    2004-07-01T23:59:59.000Z

    The purpose of this document is to discuss issues related to the implementation of each of the five down-selected INEEL/INTEC radioactive liquid waste (sodium-bearing waste - SBW) treatment alternatives and summarize information in three main areas of concern: process/technical, environmental permitting, and schedule. Major implementation options for each treatment alternative are also identified and briefly discussed. This report may touch upon, but purposely does not address in detail, issues that are programmatic in nature. Examples of these include how the SBW will be classified with respect to the Nuclear Waste Policy Act (NWPA), status of Waste Isolation Pilot Plant (WIPP) permits and waste storage availability, available funding for implementation, stakeholder issues, and State of Idaho Settlement Agreement milestones. It is assumed in this report that the SBW would be classified as a transuranic (TRU) waste suitable for disposal at WIPP, located in New Mexico, after appropriate treatment to meet transportation requirements and waste acceptance criteria (WAC).

  6. Review of Potential Candidate Stabilization Technologies for Liquid and Solid Secondary Waste Streams

    SciTech Connect (OSTI)

    Pierce, Eric M.; Mattigod, Shas V.; Westsik, Joseph H.; Serne, R. Jeffrey; Icenhower, Jonathan P.; Scheele, Randall D.; Um, Wooyong; Qafoku, Nikolla

    2010-01-30T23:59:59.000Z

    Pacific Northwest National Laboratory has initiated a waste form testing program to support the long-term durability evaluation of a waste form for secondary wastes generated from the treatment and immobilization of Hanford radioactive tank wastes. The purpose of the work discussed in this report is to identify candidate stabilization technologies and getters that have the potential to successfully treat the secondary waste stream liquid effluent, mainly from off-gas scrubbers and spent solids, produced by the Hanford Tank Waste Treatment and Immobilization Plant (WTP). Down-selection to the most promising stabilization processes/waste forms is needed to support the design of a solidification treatment unit (STU) to be added to the Effluent Treatment Facility (ETF). To support key decision processes, an initial screening of the secondary liquid waste forms must be completed by February 2010.

  7. Independent Oversight Activity Report, Hanford Waste Treatment...

    Office of Environmental Management (EM)

    Observation of the Waste Treatment and Immobilization Plant Low Activity Waste Facility Heating, Ventilation, and Air Conditioning Systems Hazards Analysis Activities...

  8. Municipal Solid Waste (MSW) to Liquid Fuels Synthesis, Volume...

    Office of Environmental Management (EM)

    1: Availability of Feedstock and Technology Municipal Solid Waste (MSW) to Liquid Fuels Synthesis, Volume 1: Availability of Feedstock and Technology Municipal solid waste (MSW) is...

  9. SECONDARY WASTE MANAGEMENT STRATEGY FOR EARLY LOW ACTIVITY WASTE TREATMENT

    SciTech Connect (OSTI)

    CRAWFORD TW

    2008-07-17T23:59:59.000Z

    This study evaluates parameters relevant to River Protection Project secondary waste streams generated during Early Low Activity Waste operations and recommends a strategy for secondary waste management that considers groundwater impact, cost, and programmatic risk. The recommended strategy for managing River Protection Project secondary waste is focused on improvements in the Effiuent Treatment Facility. Baseline plans to build a Solidification Treatment Unit adjacent to Effluent Treatment Facility should be enhanced to improve solid waste performance and mitigate corrosion of tanks and piping supporting the Effiuent Treatment Facility evaporator. This approach provides a life-cycle benefit to solid waste performance and reduction of groundwater contaminants.

  10. Animal Waste Treatment System Loan Program (Missouri)

    Broader source: Energy.gov [DOE]

    The purpose of the Animal Waste Treatment System Loan Program is to finance animal waste treatment systems for independent livestock and poultry producers at below conventional interest rates. Loan...

  11. Thermodynamic estimation of minor element distribution between immiscible liquids in Fe-Cu-based metal phase generated in melting treatment of municipal solid wastes

    SciTech Connect (OSTI)

    Lu, X. [School of Metallurgical and Ecological Engineering, The University of Science and Technology Beijing, 30 Xueyuan Road, Haidian District, Beijing 100083 (China); Nakajima, K.; Sakanakura, H. [Research Center for Material Cycles and Waste Management, National Institute for Environmental Studies (NIES), 16-2 Onogawa, Tsukuba 305-8506 (Japan); Matsubae, K. [Graduate School of Engineering, Tohoku University, 6-6-11 Aza-Aoba, Aramaki, Sendai 980-8579 (Japan); Bai, H. [School of Metallurgical and Ecological Engineering, The University of Science and Technology Beijing, 30 Xueyuan Road, Haidian District, Beijing 100083 (China); Nagasaka, T., E-mail: t-nagasaka@m.tohoku.ac.jp [Graduate School of Engineering, Tohoku University, 6-6-11 Aza-Aoba, Aramaki, Sendai 980-8579 (Japan)

    2012-06-15T23:59:59.000Z

    Graphical abstract: Display Omitted Highlights: Black-Right-Pointing-Pointer Two liquids separation of metal occurs in the melting of municipal solid waste. Black-Right-Pointing-Pointer The distribution of PGMs etc. between two liquid metal phases is studied. Black-Right-Pointing-Pointer Quite simple thermodynamic model is applied to predict the distribution ratio. Black-Right-Pointing-Pointer Au and Ag originated from WEEE are found to be concentrated into Cu-rich phase. - Abstract: Waste electrical and electronic equipment (WEEE) has become an important target in managing material cycles from the viewpoint of not only waste management and control of environmental pollution but also resource conservation. This study investigated the distribution tendency of trace elements in municipal solid waste (MSW) or incinerator ash, including valuable non-ferrous metals (Ni, Co, Cr, Mn, Mo, Ti, V, W, Zr), precious group metals (PGMs) originated from WEEE (Ag, Au, Pd, Pt), and others (Al, B, Pb, Si), between Fe-rich and Cu-rich metal phases by means of simple thermodynamic calculations. Most of the typical alloying elements for steel (Co, Cr, Mo, Nb, Ni, Si, Ti, V, and W) and Rh were preferentially distributed into the Fe-rich phase. PGMs, such as Au, Ag, and Pd, were enriched in the Cu-rich phase, whereas Pt was almost equally distributed into both phases. Since the primary metallurgical processing of Cu is followed by an electrolysis for refining, and since PGMs in crude copper have been industrially recovered from the resulting anode slime, our results indicated that Ag, Au, and Pd could be effectively recovered from MSW if the Cu-rich phase could be selectively collected.

  12. Used powdex resin for liquid waste processing

    SciTech Connect (OSTI)

    Pearson, C.J.; Bramblett, J.W.

    1995-05-01T23:59:59.000Z

    Powdex resin has traditionally been used on the Secondary side for condensate polishing. The resins on these polishers are backwashed periodically based on chemical breakthrough or high differential pressure. Upon the backwash, the ion exchange capacity on the powdex resin is not completely exhausted. In the past, this partially used powdex resin was sluiced to a liner and treated as waste for disposal. In an effort to reduce radioactivity being released from segregated, high chemical concentration wastes, the idea of trying used powdex resin was initiated. In 1992, Duke Power Company began processing problem liquid waste streams with used Secondary powdex and subsequent decanting of the waste water for release. the results have shown significant reductions in the activity of this water. This paper will detail the history, method, and the results of using Secondary powdex for liquid radwaste processing. It will also describe the benefits, such as: (1) Processing waste streams not suitable for bead resin demineralizers. (2) Ability to process large volumes of waste water in a short period of time. (3) Recycling media thought to be useless. (4) > 80% Reduction in activity of water processed. (5) Overall curies reduction. (6) Improved bead demineralizer performance.

  13. A Regulatory Analysis and Reassessment of U.S. Environmental Protection Agency Listed Hazardous Waste Numbers for Applicability to the INTEC Liquid Waste System

    SciTech Connect (OSTI)

    Gilbert, K.L.; Venneman, T.E.

    1998-12-01T23:59:59.000Z

    This report concludes that there are four listed hazardous waste numbers (F001, F002, F005, and U134) applicable to the waste in the Process Equipment Waste Evaporator (PEWE) liquid waste system at the Idaho National Engineering and Environmental Laboratory. The chemical constituents associated with these listed hazardous waste numbers, including those listed only for ignitability are identified. The RCRA Part A permit application hazardous waste numbers identify chemical constituents that may be treated or stored by the PEWE liquid waste system either as a result of a particular characteristic (40 CFR, Subpart C) or as a result of a specific process (40 CFR 261, Subpart D). The RCRA Part A permit application for the PEWE liquid waste system identifies the universe of Environmental Protection Agency (EPA) hazardous waste numbers [23 characteristic (hazardous waste codes) numbers and 105 listed numbers (four F-listed hazardous waste numbers, 20 P-listed hazardous waste numbers, and 81 U-listed hazardous waste numbers)] deemed acceptable for storage and treatment. This evaluation, however, identifies only listed wastes (and their chemical constituents) that have actually entered the PEWE liquid waste system and would, therefore, be assigned to the PEWE liquids and treatment residuals.

  14. Westinghouse Cementation Facility of Solid Waste Treatment System - 13503

    SciTech Connect (OSTI)

    Jacobs, Torsten; Aign, Joerg [Westinghouse Electric Germany GmbH, Global Waste Management, Tarpenring 6, D- 22419 Hamburg (Germany)] [Westinghouse Electric Germany GmbH, Global Waste Management, Tarpenring 6, D- 22419 Hamburg (Germany)

    2013-07-01T23:59:59.000Z

    During NPP operation, several waste streams are generated, caused by different technical and physical processes. Besides others, liquid waste represents one of the major types of waste. Depending on national regulation for storage and disposal of radioactive waste, solidification can be one specific requirement. To accommodate the global request for waste treatment systems Westinghouse developed several specific treatment processes for the different types of waste. In the period of 2006 to 2008 Westinghouse awarded several contracts for the design and delivery of waste treatment systems related to the latest CPR-1000 nuclear power plants. One of these contracts contains the delivery of four Cementation Facilities for waste treatment, s.c. 'Follow on Cementations' dedicated to three locations, HongYanHe, NingDe and YangJiang, of new CPR-1000 nuclear power stations in the People's Republic of China. Previously, Westinghouse delivered a similar cementation facility to the CPR-1000 plant LingAo II, in Daya Bay, PR China. This plant already passed the hot functioning tests successfully in June 2012 and is now ready and released for regular operation. The 'Follow on plants' are designed to package three 'typical' kind of radioactive waste: evaporator concentrates, spent resins and filter cartridges. The purpose of this paper is to provide an overview on the Westinghouse experience to design and execution of cementation facilities. (authors)

  15. Mixed waste characterization, treatment & disposal focus area

    SciTech Connect (OSTI)

    NONE

    1996-08-01T23:59:59.000Z

    The mission of the Mixed Waste Characterization, Treatment, and Disposal Focus Area (referred to as the Mixed Waste Focus Area or MWFA) is to provide treatment systems capable of treating DOE`s mixed waste in partnership with users, and with continual participation of stakeholders, tribal governments, and regulators. The MWFA deals with the problem of eliminating mixed waste from current and future storage in the DOE complex. Mixed waste is waste that contains both hazardous chemical components, subject to the requirements of the Resource Conservation and Recovery Act (RCRA), and radioactive components, subject to the requirements of the Atomic Energy Act. The radioactive components include transuranic (TRU) and low-level waste (LLW). TRU waste primarily comes from the reprocessing of spent fuel and the use of plutonium in the fabrication of nuclear weapons. LLW includes radioactive waste other than uranium mill tailings, TRU, and high-level waste, including spent fuel.

  16. Thermal treatment of organic radioactive waste

    SciTech Connect (OSTI)

    Chrubasik, A.; Stich, W. [NUKEM GmbH, Alzenau (Germany)

    1993-12-31T23:59:59.000Z

    The organic radioactive waste which is generated in nuclear and isotope facilities (power plants, research centers and other) must be treated in order to achieve a waste form suitable for long term storage and disposal. Therefore the resulting waste treatment products should be stable under influence of temperature, time, radioactivity, chemical and biological activity. Another reason for the treatment of organic waste is the volume reduction with respect to the storage costs. For different kinds of waste, different treatment technologies have been developed and some are now used in industrial scale. The paper gives process descriptions for the treatment of solid organic radioactive waste of low beta/gamma activity and alpha-contaminated solid organic radioactive waste, and the pyrolysis of organic radioactive waste.

  17. DOE mixed waste treatment capacity analysis

    SciTech Connect (OSTI)

    Ross, W.A.; Wehrman, R.R.; Young, J.R.; Shaver, S.R.

    1994-06-01T23:59:59.000Z

    This initial DOE-wide analysis compares the reported national capacity for treatment of mixed wastes with the calculated need for treatment capacity based on both a full treatment of mixed low-level and transuranic wastes to the Land Disposal Restrictions and on treatment of transuranic wastes to the WIPP waste acceptance criteria. The status of treatment capacity is reported based on a fifty-element matrix of radiation-handling requirements and functional treatment technology categories. The report defines the classifications for the assessment, describes the models used for the calculations, provides results from the analysis, and includes appendices of the waste treatment facilities data and the waste stream data used in the analysis.

  18. Using benchmarking to minimize common DOE waste streams. Volume 1, Methodology and liquid photographic waste

    SciTech Connect (OSTI)

    Levin, V.

    1994-04-01T23:59:59.000Z

    Finding innovative ways to reduce waste streams generated at Department of Energy (DOE) sites by 50% by the year 2000 is a challenge for DOE`s waste minimization efforts. This report examines the usefulness of benchmarking as a waste minimization tool, specifically regarding common waste streams at DOE sites. A team of process experts from a variety of sites, a project leader, and benchmarking consultants completed the project with management support provided by the Waste Minimization Division EM-352. Using a 12-step benchmarking process, the team examined current waste minimization processes for liquid photographic waste used at their sites and used telephone and written questionnaires to find ``best-in-class`` industrv partners willing to share information about their best waste minimization techniques and technologies through a site visit. Eastman Kodak Co., and Johnson Space Center/National Aeronautics and Space Administration (NASA) agreed to be partners. The site visits yielded strategies for source reduction, recycle/recovery of components, regeneration/reuse of solutions, and treatment of residuals, as well as best management practices. An additional benefit of the work was the opportunity for DOE process experts to network and exchange ideas with their peers at similar sites.

  19. UW-Approved Waste Disposal, Recycling and Treatment Sites Hazardous waste disposal at the University of Washington is coordinated by the EH&S Environmental Programs Office

    E-Print Network [OSTI]

    Wilcock, William

    solid waste, use the approved facilities listed below. This document is primarily intended & sludge Seattle, WA Ventilation Power Cleaning Vactor & parking garage waste Seattle, WA King County Treatment Plant Liquids & sludge Seattle, WA La Farge Cement Kiln Liquids & sludge Seattle, WA Cemex Liquids

  20. Independent Oversight Review, Waste Treatment and Immobilization...

    Office of Environmental Management (EM)

    August 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality This report documents the results of an independent oversight review of...

  1. Independent Oversight Review, Waste Treatment and Immobilization...

    Office of Environmental Management (EM)

    2013 May 2013 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U.S. Department of Energy (DOE) Office of Enforcement and Oversight...

  2. Independent Oversight Review, Waste Treatment and Immobilization...

    Office of Environmental Management (EM)

    2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality This report documents the results of an independent oversight review of...

  3. Independent Oversight Review, Waste Treatment and Immobilization...

    Office of Environmental Management (EM)

    2013 March 2013 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U.S. Department of Energy (DOE) Office of Enforcement and Oversight...

  4. Independent Oversight Review, Waste Treatment and Immobilization...

    Office of Environmental Management (EM)

    October 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality This report documents the results of an independent review of selected...

  5. Washington Environmental Permit Handbook - Dangerous Waste Treatment...

    Open Energy Info (EERE)

    Washington Environmental Permit Handbook - Dangerous Waste Treatment Storage Disposal Facility New Permit Jump to: navigation, search OpenEI Reference LibraryAdd to library Web...

  6. Independent Oversight Review, Advanced Mixed Waste Treatment...

    Broader source: Energy.gov (indexed) [DOE]

    April 2013 Review of Radiation Protection Program Implementation at the Advanced Mixed Waste Treatment Project of the Idaho Site This report documents an independent review of...

  7. Independent Oversight Activity Report, Hanford Waste Treatment...

    Broader source: Energy.gov (indexed) [DOE]

    Hanford Waste Treatment and Immobilization Plant Engineering Activities and Tank Farm Operations HIAR-HANFORD-2014-01-13 This Independent Oversight Activity Report documents...

  8. Enterprise Assessments Operational Awareness Record, Waste Treatment...

    Office of Environmental Management (EM)

    The review was conducted August 18-28, 2014. Enterprise Assessments Operational Awareness Record, Waste Treatment and Immobilization Plant - December 2014 More Documents &...

  9. Enterprise Assessments Operational Awareness Record, Waste Treatment...

    Office of Environmental Management (EM)

    tables. The review was conducted June 2-19, 2014. Enterprise Assessments Operational Awareness Record, Waste Treatment and Immobilization Plant - December 2014 More Documents &...

  10. Hanford Waste Treatment Plant Construction Quality Review

    Broader source: Energy.gov (indexed) [DOE]

    Safety and Health Evaluations Activity Report for the Hanford Waste Treatment Plant Construction Quality Review Dates of Activity 02142011 - 02172011 Report Preparer Joseph...

  11. Independent Oversight Review, Waste Treatment and Immobilization...

    Energy Savers [EERE]

    Plant - August 2011 August 2011 Hanford Waste Treatment and Immobilization Plant Construction Quality This report documents the results of an independent oversight review of...

  12. Independent Oversight Review, Waste Treatment and Immobilization...

    Energy Savers [EERE]

    2011 Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality This report documents the results of an independent oversight review of...

  13. Onsite Wastewater Treatment Systems: Liquid Chlorination

    E-Print Network [OSTI]

    Weaver, Richard; Lesikar, Bruce J.; Richter, Amanda; O'Neill, Courtney

    2008-10-23T23:59:59.000Z

    This publication explains the process, components, legal requirements, factors affecting performance, and maintenance needs of liquid chlorination systems for onsite wastewater treatment....

  14. Radioactive waste treatment technologies and environment

    SciTech Connect (OSTI)

    HORVATH, Jan; KRASNY, Dusan [JAVYS, PLc. - Nuclear and Decommisioning Company, PLc. (Slovakia)

    2007-07-01T23:59:59.000Z

    The radioactive waste treatment and conditioning are the most important steps in radioactive waste management. At the Slovak Electric, plc, a range of technologies are used for the processing of radioactive waste into a form suitable for disposal in near surface repository. These technologies operated by JAVYS, PLc. Nuclear and Decommissioning Company, PLc. Jaslovske Bohunice are described. Main accent is given to the Bohunice Radwaste Treatment and Conditioning Centre, Bituminization plant, Vitrification plant, and Near surface repository of radioactive waste in Mochovce and their operation. Conclusions to safe and effective management of radioactive waste in the Slovak Republic are presented. (authors)

  15. Thermal Treatment of Solid Wastes Using the Electric Arc Furnace

    SciTech Connect (OSTI)

    O'Connor, W.K.; Turner, P.C.

    1999-09-01T23:59:59.000Z

    A thermal waste treatment facility has been developed at the Albany Research Center (ARC) over the past seven years to process a wide range of heterogeneous mixed wastes, on a scale of 227 to 907 kg/h (500 to 2,000 lb/h). The current system includes a continuous feed system, a 3-phase AC, 0.8 MW graphite electrode arc furnace, and a dedicated air pollution control system (APCS) which includes a close-coupled thermal oxidizer, spray cooler, baghouse, and wet scrubber. The versatility of the complete system has been demonstrated during 5 continuous melting campaigns, ranging from 11 to 25 mt (12 to 28 st) of treated wastes per campaign, which were conducted on waste materials such as (a) municipal incinerator ash, (b) simulated low-level radioactive, high combustible-bearing mixed wastes, (c) simulated low-level radioactive liquid tank wastes, (d) heavy metal contaminated soils, and (e) organic-contaminated dredging spoils. In all cases, the glass or slag products readily passed the U.S. Environmental Protection Agency (EPA) Toxicity Characteristic Leachability Program (TCLP) test. Additional studies are currently under way on electric utility wastes, steel and aluminum industry wastes, as well as zinc smelter residues. Thermal treatment of these solid waste streams is intended to produce a metallic product along with nonhazardous glass or slag products.

  16. KKP-waste treatment and disposal

    SciTech Connect (OSTI)

    Blaser, W.; Grundke, E. [NPP Philippsburg (Germany)

    1993-12-31T23:59:59.000Z

    The study of the radwaste treatment in nuclear power plants in order to minimize the repository volume of the waste and the necessity of minimizing nuclear transports leads to new waste processing methods. The volume reduction effects of the new processing methods compared with the former ones is significant. Various types of operational waste of the two NPP`s in Philippsburg are generated as a result of the different kind of plants and their different mode of operation. Therefore the necessity of adequate waste treatment requires a new concept.

  17. DOE Selects Seven Contractors for Waste Treatment Basic Ordering...

    Office of Environmental Management (EM)

    Selects Seven Contractors for Waste Treatment Basic Ordering Agreements DOE Selects Seven Contractors for Waste Treatment Basic Ordering Agreements June 4, 2015 - 12:00pm Addthis...

  18. Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Facility...

    Office of Environmental Management (EM)

    Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Facility Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Facility August 18, 2011 - 12:00pm Addthis Idaho...

  19. Advanced Mixed Waste Treatment Project Achieves Impressive Safety...

    Office of Environmental Management (EM)

    Advanced Mixed Waste Treatment Project Achieves Impressive Safety and Production Marks Advanced Mixed Waste Treatment Project Achieves Impressive Safety and Production Marks June...

  20. Idaho Waste Treatment Facility Improves Worker Safety and Efficiency...

    Office of Environmental Management (EM)

    Waste Treatment Facility Improves Worker Safety and Efficiency, Saves Taxpayer Dollars Idaho Waste Treatment Facility Improves Worker Safety and Efficiency, Saves Taxpayer Dollars...

  1. Liquid and Gaseous Waste Operations Project Annual Operating Report CY 1999

    SciTech Connect (OSTI)

    Maddox, J.J.; Scott, C.B.

    2000-03-01T23:59:59.000Z

    A total of 5.77 x 10 7 gallons (gal) of liquid waste was decontaminated by the Process Waste Treatment Complex (PWTC) - Building 3544 ion exchange system during calendar year (CY) 1999. This averaged to 110 gpm throughout the year. An additional 3.94 x 10 6 gal of liquid waste (average of 8 gpm throughout the year) was decontaminated using the zeolite treatment system due to periods of high Cesium levels in the influent wastewater. A total of 6.17 x 10 7 gal of liquid waste (average of 118 gpm throughout the year) was decontaminated at Building 3544 during the year. During the year, the regeneration of the ion exchange resins resulted in the generation of 8.00 x 10 3 gal of Liquid Low-Level Waste (LLLW) concentrate and 9.00 x 10 2 gal of LLLW supernate. See Table 1 for a monthly summary of activities at Building 3544. Figure 1 shows a diagram of the Process Waste Collection and Transfer System and Figure 2 shows a diagram of the Building 3544 treatment process. Figures 3, 4 5, and 6 s how a comparison of operations at Building 3544 in 1997 with previous years. Figure 7 shows a comparison of annual rainfall at Oak Ridge National Laboratory (ORNL) since 1995.

  2. Detection of free liquid in containers of solidified radioactive waste

    DOE Patents [OSTI]

    Greenhalgh, Wilbur O. (Richland, WA)

    1985-01-01T23:59:59.000Z

    A method of nondestructively detecting the presence of free liquid within a sealed enclosure containing solidified waste by measuring the levels of waste at two diametrically opposite locations while slowly tilting the enclosure toward one of said locations. When the measured level remains constant at the other location, the measured level at said one location is noted and any measured difference of levels indicates the presence of liquid on the surface of the solidified waste. The absence of liquid in the enclosure is verified when the measured levels at both locations are equal.

  3. NORDIC WASTE WATER TREATMENT SLUDGE TREATMENT

    E-Print Network [OSTI]

    biogas, electricity and fertilizer from 30 000 tons of annually waste. The plant was opened in March 2008 together it an- nually produces 18,9 GWh biogas and around 10 GWh of elec- tricity. The Cambi THP ­process biological sludge, which normally is very difficult to digest and dewater. The THP treats both municipal

  4. Accelerated carbonation treatment of industrial wastes

    SciTech Connect (OSTI)

    Gunning, Peter J., E-mail: gunning_peter@hotmail.co [Centre for Contaminated Land Remediation, University of Greenwich, Chatham Maritime (United Kingdom); Hills, Colin D.; Carey, Paula J. [Centre for Contaminated Land Remediation, University of Greenwich, Chatham Maritime (United Kingdom)

    2010-06-15T23:59:59.000Z

    The disposal of industrial waste presents major logistical, financial and environmental issues. Technologies that can reduce the hazardous properties of wastes are urgently required. In the present work, a number of industrial wastes arising from the cement, metallurgical, paper, waste disposal and energy industries were treated with accelerated carbonation. In this process carbonation was effected by exposing the waste to pure carbon dioxide gas. The paper and cement wastes chemically combined with up to 25% by weight of gas. The reactivity of the wastes to carbon dioxide was controlled by their constituent minerals, and not by their elemental composition, as previously postulated. Similarly, microstructural alteration upon carbonation was primarily influenced by mineralogy. Many of the thermal wastes tested were classified as hazardous, based upon regulated metal content and pH. Treatment by accelerated carbonation reduced the leaching of certain metals, aiding the disposal of many as stable non-reactive wastes. Significant volumes of carbon dioxide were sequestrated into the accelerated carbonated treated wastes.

  5. Municipal Solid Waste (MSW) to Liquid Fuels Synthesis, Volume...

    Energy Savers [EERE]

    2: A Techno-economic Evaluation of the Production of Mixed Alcohols Municipal Solid Waste (MSW) to Liquid Fuels Synthesis, Volume 2: A Techno-economic Evaluation of the Production...

  6. Voluntary Protection Program Onsite Review, Waste Treatment Plant...

    Office of Environmental Management (EM)

    Construction Project - June 2010 Voluntary Protection Program Onsite Review, Waste Treatment Plant Construction Project - June 2010 June 2010 Evaluation to determine whether Waste...

  7. State-of-the-art report on low-level radioactive waste treatment

    SciTech Connect (OSTI)

    Kibbey, A.H.; Godbee, H.W.

    1980-09-01T23:59:59.000Z

    An attempt is made to identify the main sources of low-level radioactive wastes that are generated in the United States. To place the waste problem in perspective, rough estimates are given of the annual amounts of each generic type of waste that is generated. Most of the wet solid wastes arise from the cleanup of gaseous and liquid radioactive streams prior to discharge or recycle. The treatment of the process streams and the secondary wet solid wastes thus generated is described for each type of government or fuel cycle installation. Similarly, the institutional wet wastes are also described. The dry wastes from all sources have smilar physical and chemical characteristics in that they can be classified as compactible, noncompactible, combustible, noncombustible, or combinations thereof. The various treatment options for concentrated or solid wet wastes and for dry wastes are discussed. Among the dry-waste treatment methods are compaction, baling, and incineration, as well as chopping, cutting, and shredding. Organic materials can usually be incinerated or, in some cases, biodegraded. The filter sludges, spent resins, incinerator ashes, and concentrated liquids are usually solidified in cement, urea-formaldehyde, or unsaturated polyester resins prior to burial. Asphalt has not yet been used as a solidificaton agent in the United States, but it probably will be used in the near future. The treatment of radioactive medical and bioresearch wastes is described, but the waste from radiochenmical, pharmaceutical, and other industries is not well defined at the present time. Recovery of waste metals and treatment of hazardous contaminated wastes are discussed briefly. Some areas appearing to need more research, development, and demonstration are specifically pointed out.

  8. Medical waste treatment and decontamination system

    DOE Patents [OSTI]

    Wicks, George G. (Aiken, SC); Schulz, Rebecca L. (Aiken, SC); Clark, David E. (Gainesville, FL)

    2001-01-01T23:59:59.000Z

    The invention discloses a tandem microwave system consisting of a primary chamber in which hybrid microwave energy is used for the controlled combustion of materials. A second chamber is used to further treat the off-gases from the primary chamber by passage through a susceptor matrix subjected to additional hybrid microwave energy. The direct microwave radiation and elevated temperatures provide for significant reductions in the qualitative and quantitative emissions of the treated off gases. The tandem microwave system can be utilized for disinfecting wastes, sterilizing materials, and/or modifying the form of wastes to solidify organic or inorganic materials. The simple design allows on-site treatment of waste by small volume waste generators.

  9. Hydrophilization of Liquid Surfaces by Plasma Treatment

    E-Print Network [OSTI]

    Victor Multanen; Gilad Chaniel; Roman Grynyov; Ron Yosef Loew; Naor Siany; Edward Bormashenko

    2014-09-01T23:59:59.000Z

    The impact of the cold radiofrequency air plasma on the surface properties of silicone oils (polydimethylsiloxane) was studied. Silicone oils of various molecular masses were markedly hydrophilized by the cold air plasma treatment. A pronounced decrease of the apparent water contact angles was observed after plasma treatment. A general theoretical approach to the calculation of apparent contact angles is proposed. The treated liquid surfaces demonstrated hydrophobic recovery. The characteristic time of the hydrophobic recovery grew with the molecular mass of the silicone oil.

  10. Waste water treatment and metal recovery

    E-Print Network [OSTI]

    Braun, Paul

    Waste water treatment and metal recovery Nickel catalysts for hydrogen production Nickel and single versions of which contained cobalt, chromium, carbon, molybdenum, tungsten, and nickel. In 1911 and 1912% on their stainless steel production. The company paid sizable dividends to its owners until it was dissolved

  11. TRAITEMENT DES EFFLUENTS WASTE TREATMENT

    E-Print Network [OSTI]

    Boyer, Edmond

    residence time the production of biogas (7l-78 p. 100 CH,) was 237 1 per kg dry matter, i.e. 479 1 of CH to obtain the same amount of biogas four times quicklier. The treatment yield was improved (65 p. 100 COD). The mean production was 4931 biogas/kg degraded COD. It seems to be possible to apply that procedure

  12. Radioactive Bench-scale Steam Reformer Demonstration of a Monolithic Steam Reformed Mineralized Waste Form for Hanford Waste Treatment Plant Secondary Waste - 12306

    SciTech Connect (OSTI)

    Evans, Brent; Olson, Arlin; Mason, J. Bradley; Ryan, Kevin [THOR Treatment Technologies, LLC - 106 Newberry St. SW, Aiken, SC 29801 (United States); Jantzen, Carol; Crawford, Charles [Savannah River Nuclear Solutions (SRNL), LLC, Aiken, SC 29808 (United States)

    2012-07-01T23:59:59.000Z

    Hanford currently has 212,000 m{sup 3} (56 million gallons) of highly radioactive mixed waste stored in the Hanford tank farm. This waste will be processed to produce both high-level and low-level activity fractions, both of which are to be vitrified. Supplemental treatment options have been under evaluation for treating portions of the low-activity waste, as well as the liquid secondary waste from the low-activity waste vitrification process. One technology under consideration has been the THOR{sup R} fluidized bed steam reforming process offered by THOR Treatment Technologies, LLC (TTT). As a follow-on effort to TTT's 2008 pilot plant FBSR non-radioactive demonstration for treating low-activity waste and waste treatment plant secondary waste, TTT, in conjunction with Savannah River National Laboratory, has completed a bench scale evaluation of this same technology on a chemically adjusted radioactive surrogate of Hanford's waste treatment plant secondary waste stream. This test generated a granular product that was subsequently formed into monoliths, using a geo-polymer as the binding agent, that were subjected to compressibility testing, the Product Consistency Test and other leachability tests, and chemical composition analyses. This testing has demonstrated that the mineralized waste form, produced by co-processing waste with kaolin clay using the TTT process, is as durable as low-activity waste glass. Testing has shown the resulting monolith waste form is durable, leach resistant, and chemically stable, and has the added benefit of capturing and retaining the majority of Tc-99, I-129, and other target species at high levels. (authors)

  13. Waste Form Development for the Solidification of PDCF/MOX Liquid Waste Streams

    SciTech Connect (OSTI)

    COZZI, ALEX

    2004-02-18T23:59:59.000Z

    At the Savannah River Site, part of the Department of Energy's nuclear materials complex located in South Carolina, cementation has been selected as the solidification method for high-alpha and low-activity waste streams generated in the planned plutonium disposition facilities. A Waste Solidification Building (WSB) that will be used to treat and solidify three radioactive liquid waste streams generated by the Pit Disassembly and Conversion Facility) and the Mixed Oxide Fuel Fabrication Facility is in the preliminary design stage. The WSB is expected to treat a transuranic (TRU) waste stream composed primarily of americium and two low-level waste (LLW) streams. The acidic wastes will be concentrated in the WSB evaporator and neutralized in a cement head tank prior to solidification. A series of TRU mixes were prepared to produce waste forms exhibiting a range of processing and cured properties. The LLW mixes were prepared using the premix from the preferred TRU waste form. All of the waste forms tested passed the Toxicity Characteristic Leaching Procedure. After processing in the WSB, current plans are to dispose of the solidified TRU waste at the Waste Isolation Pilot Plant in New Mexico and the solidified LLW waste at an approved low-level waste disposal facility.

  14. Waste Treatment Technology Process Development Plan For Hanford Waste Treatment Plant Low Activity Waste Recycle

    SciTech Connect (OSTI)

    McCabe, Daniel J.; Wilmarth, William R.; Nash, Charles A.

    2013-08-29T23:59:59.000Z

    The purpose of this Process Development Plan is to summarize the objectives and plans for the technology development activities for an alternative path for disposition of the recycle stream that will be generated in the Hanford Waste Treatment Plant Low Activity Waste (LAW) vitrification facility (LAW Recycle). This plan covers the first phase of the development activities. The baseline plan for disposition of this stream is to recycle it to the WTP Pretreatment Facility, where it will be concentrated by evaporation and returned to the LAW vitrification facility. Because this stream contains components that are volatile at melter temperatures and are also problematic for the glass waste form, they accumulate in the Recycle stream, exacerbating their impact on the number of LAW glass containers. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and reducing the halides in the Recycle is a key component of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, this stream does not have a proven disposition path, and resolving this gap becomes vitally important. This task seeks to examine the impact of potential future disposition of this stream in the Hanford tank farms, and to develop a process that will remove radionuclides from this stream and allow its diversion to another disposition path, greatly decreasing the LAW vitrification mission duration and quantity of glass waste. The origin of this LAW Recycle stream will be from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW melter off-gas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover or precipitates of scrubbed components (e.g. carbonates). The soluble components are mostly sodium and ammonium salts of nitrate, chloride, and fluoride. This stream has not been generated yet, and will not be available until the WTP begins operation, causing uncertainty in its composition, particularly the radionuclide content. This plan will provide an estimate of the likely composition and the basis for it, assess likely treatment technologies, identify potential disposition paths, establish target treatment limits, and recommend the testing needed to show feasibility. Two primary disposition options are proposed for investigation, one is concentration for storage in the tank farms, and the other is treatment prior to disposition in the Effluent Treatment Facility. One of the radionuclides that is volatile and expected to be in high concentration in this LAW Recycle stream is Technetium-99 ({sup 99}Tc), a long-lived radionuclide with a half-life of 210,000 years. Technetium will not be removed from the aqueous waste in the Hanford Waste Treatment and Immobilization Plant (WTP), and will primarily end up immobilized in the LAW glass, which will be disposed in the Integrated Disposal Facility (IDF). Because {sup 99}Tc has a very long half-life and is highly mobile, it is the largest dose contributor to the Performance Assessment (PA) of the IDF. Other radionuclides that are also expected to be in appreciable concentration in the LAW Recycle are {sup 129}I, {sup 90}Sr, {sup 137}Cs, and {sup 241}Am. The concentrations of these radionuclides in this stream will be much lower than in the LAW, but they will still be higher than limits for some of the other disposition pathways currently available. Although the baseline process will recycle this stream to the Pretreatment Facility, if the LAW facility begins operation first, this stream will not have a disposition path internal to WTP. One potential solution is to return the stream to the tank farms where it can be evaporated in the 242-A evaporator, or perhaps deploy an auxiliary evaporator to concentrate it prior to return to the tank farms. In either case, testing is needed to evaluat

  15. Evaluation of prospective hazardous waste treatment technologies for use in processing low-level mixed wastes at Rocky Flats

    SciTech Connect (OSTI)

    McGlochlin, S.C.; Harder, R.V.; Jensen, R.T.; Pettis, S.A.; Roggenthen, D.K.

    1990-09-18T23:59:59.000Z

    Several technologies for destroying or decontaminating hazardous wastes were evaluated (during early 1988) as potential processes for treating low-level mixed wastes destined for destruction in the Fluidized Bed Incinerator. The processes that showed promise were retained for further consideration and placed into one (or more) of three categories based on projected availability: short, intermediate, and long-term. Three potential short-term options were identified for managing low-level mixed wastes generated or stored at the Rocky Flats Plant (operated by Rockwell International in 1988). These options are: (1) Continue storing at Rocky Flats, (2) Ship to Nevada Test Site for landfill disposal, or (3) Ship to the Idaho National Engineering Laboratory for incineration in the Waste Experimental Reduction Facility. The third option is preferable because the wastes will be destroyed. Idaho National Engineering Laboratory has received interim status for processing solid and liquid low-level mixed wastes. However, low-level mixed wastes will continue to be stored at Rocky Flats until the Department of Energy approval is received to ship to the Nevada Test Site or Idaho National Engineering Laboratory. Potential intermediate and long-term processes were identified; however, these processes should be combined into complete waste treatment systems'' that may serve as alternatives to the Fluidized Bed Incinerator. Waste treatment systems will be the subject of later work. 59 refs., 2 figs.

  16. Process for immobilizing radioactive boric acid liquid wastes

    DOE Patents [OSTI]

    Greenhalgh, Wilbur O. (Richland, WA)

    1986-01-01T23:59:59.000Z

    A method of immobilizing boric acid liquid wastes containing radionuclides by neutralizing the solution and evaporating the resulting precipitate to near dryness. The dry residue is then fused into a reduced volume, insoluble, inert, solid form containing substantially all the radionuclides.

  17. Process for immobilizing radioactive boric acid liquid wastes

    DOE Patents [OSTI]

    Greenhalgh, W.O.

    1984-05-10T23:59:59.000Z

    Disclosed is a method of immobilizing boric acid liquid wastes containing radionuclides by neutralizing the solution and evaporating the resulting precipitate to near dryness. The dry residue is then fused into a reduced volume, insoluble, inert, solid form containing substantially all the radionuclides.

  18. Iraq liquid radioactive waste tanks maintenance and monitoring program plan.

    SciTech Connect (OSTI)

    Dennis, Matthew L.; Cochran, John Russell; Sol Shamsaldin, Emad (Iraq Ministry of Science and Technology)

    2011-10-01T23:59:59.000Z

    The purpose of this report is to develop a project management plan for maintaining and monitoring liquid radioactive waste tanks at Iraq's Al-Tuwaitha Nuclear Research Center. Based on information from several sources, the Al-Tuwaitha site has approximately 30 waste tanks that contain varying amounts of liquid or sludge radioactive waste. All of the tanks have been non-operational for over 20 years and most have limited characterization. The program plan embodied in this document provides guidance on conducting radiological surveys, posting radiation control areas and controlling access, performing tank hazard assessments to remove debris and gain access, and conducting routine tank inspections. This program plan provides general advice on how to sample and characterize tank contents, and how to prioritize tanks for soil sampling and borehole monitoring.

  19. Digestion of frozen/thawed food waste in the hybrid anaerobic solid-liquid system

    SciTech Connect (OSTI)

    Stabnikova, O. [School of Civil and Environmental Engineering, Nanyang Technological University, 50 Nanyang Avenue, Singapore 639798 (Singapore)], E-mail: costab@ntu.edu.sg; Liu, X.Y.; Wang, J.Y. [School of Civil and Environmental Engineering, Nanyang Technological University, 50 Nanyang Avenue, Singapore 639798 (Singapore)

    2008-07-01T23:59:59.000Z

    The hybrid anaerobic solid-liquid (HASL) system, which is a modified two-phase anaerobic digester, is to be used in an industrial scale operation to minimize disposal of food waste at incineration plants in Singapore. The aim of the present research was to evaluate freezing/thawing of food waste as a pre-treatment for its anaerobic digestion in the HASL system. The hydrolytic and fermentation processes in the acidogenic reactor were enhanced when food waste was frozen for 24 h at -20 deg. C and then thawed for 12 h at 25 deg. C (experiment) in comparison with fresh food waste (control). The highest dissolved COD concentrations in the leachate from the acidogenic reactors were 16.9 g/l on day 3 in the control and 18.9 g/l on day 1 in the experiment. The highest VFA concentrations in the leachate from the acidogenic reactors were 11.7 g/l on day 3 in the control and 17.0 g/l on day 1 in the experiment. The same volume of methane was produced during 12 days in the control and 7 days in the experiment. It gave the opportunity to diminish operational time of batch process by 42%. The effect of freezing/thawing of food waste as pre-treatment for its anaerobic digestion in the HASL system was comparable with that of thermal pre-treatment of food waste at 150 deg. C for 1 h. However, estimation of energy required either to heat the suspended food waste to 150 deg. C or to freeze the same quantity of food waste to -20 deg. C showed that freezing pre-treatment consumes about 3 times less energy than thermal pre-treatment.

  20. Emissions model of waste treatment operations at the Idaho Chemical Processing Plant

    SciTech Connect (OSTI)

    Schindler, R.E.

    1995-03-01T23:59:59.000Z

    An integrated model of the waste treatment systems at the Idaho Chemical Processing Plant (ICPP) was developed using a commercially-available process simulation software (ASPEN Plus) to calculate atmospheric emissions of hazardous chemicals for use in an application for an environmental permit to operate (PTO). The processes covered by the model are the Process Equipment Waste evaporator, High Level Liquid Waste evaporator, New Waste Calcining Facility and Liquid Effluent Treatment and Disposal facility. The processes are described along with the model and its assumptions. The model calculates emissions of NO{sub x}, CO, volatile acids, hazardous metals, and organic chemicals. Some calculated relative emissions are summarized and insights on building simulations are discussed.

  1. Combustible radioactive waste treatment by incineration and chemical digestion

    SciTech Connect (OSTI)

    Stretz, L.A.; Crippen, M.D.; Allen, C.R.

    1980-05-28T23:59:59.000Z

    A review is given of present and planned combustible radioactive waste treatment systems in the US. Advantages and disadvantages of various systems are considered. Design waste streams are discussed in relation to waste composition, radioactive contaminants by amount and type, and special operating problems caused by the waste.

  2. Evaluation of interim and final waste forms for the newly generated liquid low-level waste flowsheet

    SciTech Connect (OSTI)

    Abotsi, G.M.K. [Clark Atlanta Univ., GA (United States); Bostick, D.T.; Beck, D.E. [Oak Ridge National Lab., TN (United States)] [and others

    1996-05-01T23:59:59.000Z

    The purpose of this review is to evaluate the final forms that have been proposed for radioactive-containing solid wastes and to determine their application to the solid wastes that will result from the treatment of newly generated liquid low-level waste (NGLLLW) and Melton Valley Storage Tank (MVST) supernate at the Oak Ridge National Laboratory (ORNL). Since cesium and strontium are the predominant radionuclides in NGLLLW and MVST supernate, this review is focused on the stabilization and solidification of solid wastes containing these radionuclides in cement, glass, and polymeric materials-the principal waste forms that have been tested with these types of wastes. Several studies have shown that both cesium and strontium are leached by distilled water from solidified cement, although the leachabilities of cesium are generally higher than those of strontium under similar conditions. The situation is exacerbated by the presence of sulfates in the solution, as manifested by cracking of the grout. Additives such as bentonite, blast-furnace slag, fly ash, montmorillonite, pottery clay, silica, and zeolites generally decrease the cesium and strontium release rates. Longer cement curing times (>28 d) and high ionic strengths of the leachates, such as those that occur in seawater, also decrease the leach rates of these radionuclides. Lower cesium leach rates are observed from vitrified wastes than from grout waste forms. However, significant quantities of cesium are volatilized due to the elevated temperatures required to vitrify the waste. Hence, vitrification will generally require the use of cleanup systems for the off-gases to prevent their release into the atmosphere.

  3. Tank waste treatment science task quarterly report, April 1995--June 1995

    SciTech Connect (OSTI)

    LaFemina, J.P.

    1995-07-01T23:59:59.000Z

    This report describes the work performed by the Pacific Northwest Laboratory (PNL) during the third quarter of FY 1995 under the Tank Waste Treatment Science Task of the Tank Waste Remediation System (TWRS) Pretreatment Technology Development Project. Work was performed in the following areas: (1) analytical methods development, (2) sludge dissolution modeling, (3) sludge characterization studies, (4) sludge component speciation, (5) pretreatment chemistry evaluation, and (6) colloidal studies for solid-liquid separations.

  4. The Hybrid Treatment Process for mixed radioactive and hazardous waste treatment

    SciTech Connect (OSTI)

    Ross, W.A.; Kindle, C.H.

    1992-06-01T23:59:59.000Z

    This paper describes a new process for treating mixed hazardous and radioactive waste, commonly called mixed waste. The process is called the Hybrid Treatment Process (HTP), so named because it is built on the 20 years of experience with vitrification of wastes in melters, and the 12 years of experience with treatment of wastes by the in situ vitrification (ISV) process. It also uses techniques from several additional technologies. Mixed wastes are being generated by both the US Department of Energy (DOE) and by commercial sources. The wastes are those that contain both a hazardous waste regulated under the US Environmental Protection Agency's (EPA) Resource, Conservation, and Recovery Act (RCRA) regulations and a radioactive waste with source, special nuclear, or byproduct materials. The dual regulation of the wastes increases the complexity of the treatment, handling, and storage of the waste. The DOE is the largest holder and generator of mixed waste. Its mixed wastes are classified as either high-level, transuranic (TRU), or low-level waste (LLW). High-level mixed wastes will be treated in vitrification plants. Transuranic wastes may be disposed of without treatment by obtaining a no-migration variance from the EPA. Lowlevel wastes, however, will require treatment, but treatment systems with sufficient capacity are not yet available to DOE. Various facilities are being proposed for the treatment of low-level waste. The concept described in this paper represents one option for establishing that treatment capacity.

  5. The Hybrid Treatment Process for mixed radioactive and hazardous waste treatment

    SciTech Connect (OSTI)

    Ross, W.A.; Kindle, C.H.

    1992-06-01T23:59:59.000Z

    This paper describes a new process for treating mixed hazardous and radioactive waste, commonly called mixed waste. The process is called the Hybrid Treatment Process (HTP), so named because it is built on the 20 years of experience with vitrification of wastes in melters, and the 12 years of experience with treatment of wastes by the in situ vitrification (ISV) process. It also uses techniques from several additional technologies. Mixed wastes are being generated by both the US Department of Energy (DOE) and by commercial sources. The wastes are those that contain both a hazardous waste regulated under the US Environmental Protection Agency`s (EPA) Resource, Conservation, and Recovery Act (RCRA) regulations and a radioactive waste with source, special nuclear, or byproduct materials. The dual regulation of the wastes increases the complexity of the treatment, handling, and storage of the waste. The DOE is the largest holder and generator of mixed waste. Its mixed wastes are classified as either high-level, transuranic (TRU), or low-level waste (LLW). High-level mixed wastes will be treated in vitrification plants. Transuranic wastes may be disposed of without treatment by obtaining a no-migration variance from the EPA. Lowlevel wastes, however, will require treatment, but treatment systems with sufficient capacity are not yet available to DOE. Various facilities are being proposed for the treatment of low-level waste. The concept described in this paper represents one option for establishing that treatment capacity.

  6. Pyrolysis/Steam Reforming Technology for Treatment of TRU Orphan Wastes

    SciTech Connect (OSTI)

    Mason, J. B.; McKibbin, J.; Schmoker, D.; Bacala, P.

    2003-02-27T23:59:59.000Z

    Certain transuranic (TRU) waste streams within the Department of Energy (DOE) complex cannot be disposed of at the Waste Isolation Pilot Plant (WIPP) because they do not meet the shipping requirements of the TRUPACT-II or the disposal requirements of the Waste Analysis Plan (WAP) in the WIPP RCRA Part B Permit. These waste streams, referred to as orphan wastes, cannot be shipped or disposed of because they contain one or more prohibited items, such as liquids, volatile organic compounds (VOCs), hydrogen gas, corrosive acids or bases, reactive metals, or high concentrations of polychlorinated biphenyl (PCB), etc. The patented, non-incineration, pyrolysis and steam reforming processes marketed by THOR Treatment Technologies LLC removes all of these prohibited items from drums of TRU waste and produces a dry, inert, inorganic waste material that meets the existing TRUPACT-II requirements for shipping, as well as the existing WAP requirements for disposal of TRU waste at WIPP. THOR Treatment Technologies is a joint venture formed in June 2002 by Studsvik, Inc. (Studsvik) and Westinghouse Government Environmental Services Company LLC (WGES) to further develop and deploy Studsvik's patented THORSM technology within the DOE and Department of Defense (DoD) markets. The THORSM treatment process is a commercially proven system that has treated over 100,000 cu. ft. of nuclear waste from commercial power plants since 1999. Some of this waste has had contact dose rates of up to 400 R/hr. A distinguishing characteristic of the THORSM process for TRU waste treatment is the ability to treat drums of waste without removing the waste contents from the drum. This feature greatly minimizes criticality and contamination issues for processing of plutonium-containing wastes. The novel features described herein are protected by issued and pending patents.

  7. Analysis of waste treatment requirements for DOE mixed wastes: Technical basis

    SciTech Connect (OSTI)

    NONE

    1995-02-01T23:59:59.000Z

    The risks and costs of managing DOE wastes are a direct function of the total quantities of 3wastes that are handled at each step of the management process. As part of the analysis of the management of DOE low-level mixed wastes (LLMW), a reference scheme has been developed for the treatment of these wastes to meet EPA criteria. The treatment analysis in a limited form was also applied to one option for treatment of transuranic wastes. The treatment requirements in all cases analyzed are based on a reference flowsheet which provides high level treatment trains for all LLMW. This report explains the background and basis for that treatment scheme. Reference waste stream chemical compositions and physical properties including densities were established for each stream in the data base. These compositions are used to define the expected behavior for wastes as they pass through the treatment train. Each EPA RCRA waste code was reviewed, the properties, chemical composition, or characteristics which are of importance to waste behavior in treatment were designated. Properties that dictate treatment requirements were then used to develop the treatment trains and identify the unit operations that would be included in these trains. A table was prepared showing a correlation of the waste physical matrix and the waste treatment requirements as a guide to the treatment analysis. The analysis of waste treatment loads is done by assigning wastes to treatment steps which would achieve RCRA compliant treatment. These correlation`s allow one to examine the treatment requirements in a condensed manner and to see that all wastes and contaminant sets are fully considered.

  8. Industrial Technology of Decontamination of Liquid Radioactive Waste in SUE MosSIA 'Radon' - 12371

    SciTech Connect (OSTI)

    Adamovich, Dmitry V.; Neveykin, Petr P.; Karlin, Yuri V.; Savkin, Alexander E. [SUE MosSIA 'Radon', 7th Rostovsky lane 2/14, Moscow 119121 (Russian Federation)

    2012-07-01T23:59:59.000Z

    SUE MosSIA 'RADON' - this enterprise was created more than 50 years ago, which deals with the recycling of radioactive waste and conditioning of spent sources of radiation in stationary and mobile systems in the own factory and operating organizations. Here is represented the experience SUE MosSIA 'Radon' in the field of the management with liquid radioactive waste. It's shown, that the activity of SUE MosSIA 'RADON' is developing in three directions - improvement of technical facilities for treatment of radioactive waters into SUE MosSIA 'RADON' development of mobile equipment for the decontamination of radioactive waters in other organizations, development of new technologies for decontamination of liquid radioactive wastes as part of various domestic Russian and international projects including those related to the operation of nuclear power and nuclear submarines. SUE MosSIA 'RADON' has processed more than 270 thousand m{sup 3} of radioactive water, at that more than 7000 m{sup 3} in other organizations for more than 50 years. It is shown that a number of directions, particularly, the development of mobile modular units for decontamination of liquid radioactive waste, SUE MosSIA 'RADON' is a leader in the world. (authors)

  9. Mixed and low-level waste treatment facility project. Volume 3, Waste treatment technologies (Draft)

    SciTech Connect (OSTI)

    Not Available

    1992-04-01T23:59:59.000Z

    The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies.

  10. Selection of liquid-level monitoring method for the Oak Ridge National Laboratory inactive liquid low-level waste tanks, remedial investigation/feasibility study

    SciTech Connect (OSTI)

    Not Available

    1994-11-01T23:59:59.000Z

    Several of the inactive liquid low-level waste (LLLW) tanks at Oak Ridge National Laboratory contain residual wastes in liquid or solid (sludge) form or both. A plan of action has been developed to ensure that potential environmental impacts from the waste remaining in the inactive LLLW tank systems are minimized. This document describes the evaluation and selection of a methodology for monitoring the level of the liquid in inactive LLLW tanks. Criteria are established for comparison of existing level monitoring and leak testing methods; a preferred method is selected and a decision methodology for monitoring the level of the liquid in the tanks is presented for implementation. The methodology selected can be used to continuously monitor the tanks pending disposition of the wastes for treatment and disposal. Tanks that are empty, are scheduled to be emptied in the near future, or have liquid contents that are very low risk to the environment were not considered to be candidates for installing level monitoring. Tanks requiring new monitoring equipment were provided with conductivity probes; tanks with existing level monitoring instrumentation were not modified. The resulting data will be analyzed to determine inactive LLLW tank liquid level trends as a function of time.

  11. Independent Oversight Review, Hanford Waste Treatment and Immobilizati...

    Office of Environmental Management (EM)

    December 2013 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality This report documents the results of an independent oversight review of...

  12. Independent Oversight Review, Hanford Site Waste Treatment and...

    Office of Environmental Management (EM)

    2014 June 2014 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality This report documents the results of an independent oversight review of...

  13. Enterprise Assessments Review, Hanford Waste Treatment and Immobilizat...

    Office of Environmental Management (EM)

    January, 2015 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U.S. Department of Energy Office of Enterprise Assessments (EA)...

  14. Enterprise Assessments Review, Hanford Site Waste Treatment and...

    Office of Environmental Management (EM)

    September 2014 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U.S. Department of Energy independent Office of Enterprise Assessments...

  15. Oregon Procedure and Criteria for Hazardous Waste Treatment,...

    Open Energy Info (EERE)

    Oregon Procedure and Criteria for Hazardous Waste Treatment, Storage or Disposal Permits Fact Sheet Jump to: navigation, search OpenEI Reference LibraryAdd to library Permitting...

  16. Enterprise Assessments Review, Hanford Waste Treatment and Immobilizat...

    Office of Environmental Management (EM)

    Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality January 2015 Office of Nuclear Safety and Environmental Assessments Office of Environment,...

  17. Independent Oversight Review, Hanford Waste Treatment and Immobilizati...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    2014 March 2014 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality This report documents the results of an independent oversight review of...

  18. Independent Oversight Review, Hanford Site Waste Treatment and...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    August 2013 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U.S. Department of Energy (DOE) Office of Enforcement and Oversight...

  19. Bechtel National Inc. Waste Treatment Plant Construction Project...

    Broader source: Energy.gov (indexed) [DOE]

    June 2010 Bechtel National Incorporated Waste Treatment Plant Construction Project Report from the Department of Energy Voluntary Protection Program Onsite Review June 14-18, 2010...

  20. Biotechnology for environmental control and waste treatment

    SciTech Connect (OSTI)

    Donaldson, T.L.; Harris, M.T.; Lee, D.D.; Walker, J.F.; Strandberg, G.W.

    1985-01-01T23:59:59.000Z

    A slide show is reproduced here to review the technology of anaerobic digestion as a process for cleaning waste waters from municipal and industry wastes. Radioactive wastes are addressed also. (PSB)

  1. Figure-of-merit analysis and cost effectiveness of low-level radioactive waste treatment systems

    SciTech Connect (OSTI)

    Cox, N.D.; Falconer, K.L.; McCormack, M.D.; Hootman, H.D.; Thompson, T.K.

    1982-01-01T23:59:59.000Z

    Two studies were performed to assess low-level waste treatment systems that are available commercially for volume reduction and/or solidification. In the first, a Figure-of-Merit (FOM) decision analysis technique was used to evaluate fourteen low-level radioactive waste processing systems on their ability to treat power reactor wastes. The assessment of the various processing systems was accomplished using a five member task force. The systems were judged on eleven major criteria and twenty subcriteria. The system judged superior to all the others was compaction of dry wastes with liquid wastes and sludges being directly incorporated into concrete. This was also the lowest cost system. The controlled air incinerator was judged the preferred incineration process. The Werner-Pfleider bitumen extruder was the preferred liquid waste treatment system. In the second study, the cost economy of volume reduction measured in land disposal dollars was investigated. The greatest cost savings with volume reduction were realized with a BWR using a deep bed condensate polishing system; the least with a PWR with condensate polishing. For both BWR systems and PWRs without condensate cleanup, over 80% of the savings in land disposal dollars resulted from volume reduction of liquid waste streams (concentrated liquids and filter sludge). For a PWR with a condensate polishing system, which had the least cost effective system for volume reduction, about one-third of the savings resulting from incineration of spent resin and compactible trash was offset by the increased expense of casks required for transporting concentrated liquids which have undergone additional volume reduction.

  2. An evaluation of neutralization for processing sodium-bearing liquid waste

    SciTech Connect (OSTI)

    Chipman, N.A.; Engelgau, G.O.; Berreth, J.R.

    1989-01-01T23:59:59.000Z

    This report addresses an alternative concept for potentially managing the sodium-bearing liquid waste generated at the Idaho Chemical Processing Plant from the current method of calcining a blend of sodium waste and high-level liquid waste. The concept is based on removing the radioactive components from sodium-bearing waste by neutralization and grouting the resulting low-level waste for on-site near-surface disposal. Solidifying the sodium waste as a remote-handled transuranic waste is not considered to be practical because of excessive costs and inability to dispose of the waste in a timely fashion. Although neutralization can remove most radioactive components to provide feed for a solidified low-level waste, and can reduce liquid inventories four to nine years more rapidly than the current practice of blending sodium-bearing liquid waste with first-cycle raffinite, the alternative will require major new facilities and will generate large volumes of low-level waste. Additional facility and operating costs are estimated to be at least $500 million above the current practice of blending and calcining. On-site, low-level waste disposal may be technically difficult and conflict which national and state policies. Therefore, it is recommended that the current practice of calcining a blend of sodium-bearing liquid waste and high-level liquid waste be continued to minimize overall cost and process complexities. 17 refs., 4 figs., 16 tabs.

  3. Potential radiation damage: Storage tanks for liquid radioactive waste

    SciTech Connect (OSTI)

    Caskey, G.R. Jr.

    1992-08-21T23:59:59.000Z

    High level waste at SRS is stored in carbon steel tanks constructed during the period 1951 to 1981. This waste contains radionuclides that decay by alpha, beta, or gamma emission or are spontaneous neutronsources. Thus, a low intensity radiation field is generated that is capable of causing displacement damage to the carbon steel. The potential for degradation of mechanical properties was evaluated by comparing the estimated displacement damage with published data relating changes in Charpy V-notch (CVN) impact energy to neutron exposure. Experimental radiation data was available for three of the four grades of carbonsteel from which the tanks were constructed and is applicable to all four steels. Estimates of displacement damage arising from gamma and neutron radiation have been made based on the radionuclide contents for high level waste that are cited in the Safety Analysis Report (SAR) for the Liquid Waste Handling Facilities in the 200-Area. Alpha and beta emissions do not penetrate carbon steel to a sufficient depth to affect the bulk properties of the tank walls but may aggravate corrosion processes. The damage estimates take into account the source of the waste (F- or H-Area), the several types of tank service, and assume wateras an attenuating medium. Estimates of displacement damage are conservative because they are based on the highest levels of radionuclide contents reported in the SAR and continuous replenishment of the radionuclides.

  4. Hanford Site waste treatment/storage/disposal integration

    SciTech Connect (OSTI)

    MCDONALD, K.M.

    1999-02-24T23:59:59.000Z

    In 1998 Waste Management Federal Services of Hanford, Inc. began the integration of all low-level waste, mixed waste, and TRU waste-generating activities across the Hanford site. With seven contractors, dozens of generating units, and hundreds of waste streams, integration was necessary to provide acute waste forecasting and planning for future treatment activities. This integration effort provides disposition maps that account for waste from generation, through processing, treatment and final waste disposal. The integration effort covers generating facilities from the present through the life-cycle, including transition and deactivation. The effort is patterned after the very successful DOE Complex EM Integration effort. Although still in the preliminary stages, the comprehensive onsite integration effort has already reaped benefits. These include identifying significant waste streams that had not been forecast, identifying opportunities for consolidating activities and services to accelerate schedule or save money; and identifying waste streams which currently have no path forward in the planning baseline. Consolidation/integration of planned activities may also provide opportunities for pollution prevention and/or avoidance of secondary waste generation. A workshop was held to review the waste disposition maps, and to identify opportunities with potential cost or schedule savings. Another workshop may be held to follow up on some of the long-term integration opportunities. A change to the Hanford waste forecast data call would help to align the Solid Waste Forecast with the new disposition maps.

  5. Production of metal waste forms from spent fuel treatment

    SciTech Connect (OSTI)

    Westphal, B.R.; Keiser, D.D.; Rigg, R.H.; Laug, D.V.

    1995-02-01T23:59:59.000Z

    Treatment of spent nuclear fuel at Argonne National Laboratory consists of a pyroprocessing scheme in which the development of suitable waste forms is being advanced. Of the two waste forms being proposed, metal and mineral, the production of the metal waste form utilizes induction melting to stabilize the waste product. Alloying of metallic nuclear materials by induction melting has long been an Argonne strength and thus, the transition to metallic waste processing seems compatible. A test program is being initiated to coalesce the production of the metal waste forms with current induction melting capabilities.

  6. Global Nuclear Energy Partnership Waste Treatment Baseline

    SciTech Connect (OSTI)

    Dirk Gombert; William Ebert; James Marra; Robert Jubin; John Vienna

    2008-05-01T23:59:59.000Z

    The Global Nuclear Energy Partnership program (GNEP) is designed to demonstrate a proliferation-resistant and sustainable integrated nuclear fuel cycle that can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline of waste forms was recommended for the safe disposition of waste streams. Waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness and availability may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms.

  7. Treatment of halogen-containing waste and other waste materials

    DOE Patents [OSTI]

    Forsberg, C.W.; Beahm, E.C.; Parker, G.W.

    1997-03-18T23:59:59.000Z

    A process is described for treating a halogen-containing waste material. The process provides a bath of molten glass containing a sacrificial metal oxide capable of reacting with a halogen in the waste material. The sacrificial metal oxide is present in the molten glass in at least a stoichiometric amount with respect to the halogen in the waste material. The waste material is introduced into the bath of molten glass to cause a reaction between the halogen in the waste material and the sacrificial metal oxide to yield a metal halide. The metal halide is a gas at the temperature of the molten glass. The gaseous metal halide is separated from the molten glass and contacted with an aqueous scrubber solution of an alkali metal hydroxide to yield a metal hydroxide or metal oxide-containing precipitate and a soluble alkali metal halide. The precipitate is then separated from the aqueous scrubber solution. The molten glass containing the treated waste material is removed from the bath as a waste glass. The process of the invention can be used to treat all types of waste material including radioactive wastes. The process is particularly suited for separating halogens from halogen-containing wastes. 3 figs.

  8. Treatment of halogen-containing waste and other waste materials

    DOE Patents [OSTI]

    Forsberg, Charles W. (Oak Ridge, TN); Beahm, Edward C. (Oak Ridge, TN); Parker, George W. (Concord, TN)

    1997-01-01T23:59:59.000Z

    A process for treating a halogen-containing waste material. The process provides a bath of molten glass containing a sacrificial metal oxide capable of reacting with a halogen in the waste material. The sacrificial metal oxide is present in the molten glass in at least a stoichiometric amount with respect to the halogen in the waste material. The waste material is introduced into the bath of molten glass to cause a reaction between the halogen in the waste material and the sacrificial metal oxide to yield a metal halide. The metal halide is a gas at the temperature of the molten glass. The gaseous metal halide is separated from the molten glass and contacted with an aqueous scrubber solution of an alkali metal hydroxide to yield a metal hydroxide or metal oxide-containing precipitate and a soluble alkali metal halide. The precipitate is then separated from the aqueous scrubber solution. The molten glass containing the treated waste material is removed from the bath as a waste glass. The process of the invention can be used to treat all types of waste material including radioactive wastes. The process is particularly suited for separating halogens from halogen-containing wastes.

  9. Liquid and Gaseous Waste Operations Department annual operating report, CY 1992

    SciTech Connect (OSTI)

    Gillespie, M.A.; Maddox, J.J.; Scott, C.B.

    1993-03-01T23:59:59.000Z

    A total of 6.05 x 10{sup 7} gal of liquid waste was decontaminated by the Process Waste Treatment Plant (PWTP) ion exchange system during CY 1992. This averaged to 115 gpm throughout the year. When necessary, a wastewater sidestream of 50--80 gpm was treated through the use of a natural zeolite treatment system. An additional 8.00 x 10{sup 6} gal (average of 15 gpm throughout the year) were treated by the zeolite system. Therefore, the average total flow treated at the PWTP for CY 1992 was 130 gpm. In mid-June, the zeolite system was repiped to allow it the capability to treat the ion exchange system`s discharge due to rising Cs problems in the wastewater. While being used to treat the ion exchange system`s discharge, it cannot treat a sidestream of wastewater. During the year, the regeneration of the cation exchange resins resulted in the generation of 7.83 x 10{sup 3} gal of liquid low-level waste (LLLW) concentrate and 1.15 x 10{sup 4} gal of LLLW evaporator feed. The head-end softening process (precipitation/clarification) generated 604 drums (4.40 x 10{sup 3} ft{sup 3}) of solid low-level waste sludge. The zeolite treatment system generated approximately 8.40 x 10{sup 2} ft{sup 3} of spent zeolite resin, which was turned over to the Solid Waste Operations Department for disposal. See Table 1 for a monthly summary of activities at the PWTP. Figures 1, 2, 3, and 4 show a comparison of operations at the PWTP in 1992 with previous years. Figure 5 shows a comparison of annual rainfall at Oak Ridge National Laboratory (ORNL) since 1987. A total of 1.55 x 10{sup 8} gal of liquid waste (average of 294 gpm throughout the year) was treated at the Nonradiological Wastewater Treatment Plant (NRWTP). Of this amount, 1.40 x 10{sup 7} gal were treated by the precipitation/clarification process for removal of heavy metals. Twenty-five boxes (1.60 x 10{sup 3} ft{sup 3}) of solid sludge generated by the precipitation/clarification process were removed from the filter press room.

  10. Liquid and Gaseous Waste Operations Department annual operating report, CY 1992

    SciTech Connect (OSTI)

    Gillespie, M.A.; Maddox, J.J.; Scott, C.B.

    1993-03-01T23:59:59.000Z

    A total of 6.05 x 10[sup 7] gal of liquid waste was decontaminated by the Process Waste Treatment Plant (PWTP) ion exchange system during CY 1992. This averaged to 115 gpm throughout the year. When necessary, a wastewater sidestream of 50--80 gpm was treated through the use of a natural zeolite treatment system. An additional 8.00 x 10[sup 6] gal (average of 15 gpm throughout the year) were treated by the zeolite system. Therefore, the average total flow treated at the PWTP for CY 1992 was 130 gpm. In mid-June, the zeolite system was repiped to allow it the capability to treat the ion exchange system's discharge due to rising Cs problems in the wastewater. While being used to treat the ion exchange system's discharge, it cannot treat a sidestream of wastewater. During the year, the regeneration of the cation exchange resins resulted in the generation of 7.83 x 10[sup 3] gal of liquid low-level waste (LLLW) concentrate and 1.15 x 10[sup 4] gal of LLLW evaporator feed. The head-end softening process (precipitation/clarification) generated 604 drums (4.40 x 10[sup 3] ft[sup 3]) of solid low-level waste sludge. The zeolite treatment system generated approximately 8.40 x 10[sup 2] ft[sup 3] of spent zeolite resin, which was turned over to the Solid Waste Operations Department for disposal. See Table 1 for a monthly summary of activities at the PWTP. Figures 1, 2, 3, and 4 show a comparison of operations at the PWTP in 1992 with previous years. Figure 5 shows a comparison of annual rainfall at Oak Ridge National Laboratory (ORNL) since 1987. A total of 1.55 x 10[sup 8] gal of liquid waste (average of 294 gpm throughout the year) was treated at the Nonradiological Wastewater Treatment Plant (NRWTP). Of this amount, 1.40 x 10[sup 7] gal were treated by the precipitation/clarification process for removal of heavy metals. Twenty-five boxes (1.60 x 10[sup 3] ft[sup 3]) of solid sludge generated by the precipitation/clarification process were removed from the filter press room.

  11. Idaho Site Launches Corrective Actions Before Restarting Waste Treatment Facility

    Broader source: Energy.gov [DOE]

    IDAHO FALLS, Idaho – The Idaho site and its cleanup contractor have launched a series of corrective actions they will complete before safely resuming startup operations at the Integrated Waste Treatment Unit (IWTU) following an incident in June that caused the new waste treatment facility to shut down.

  12. Challenges when performing economic optimization of waste treatment: A review

    SciTech Connect (OSTI)

    Juul, N., E-mail: njua@dtu.dk [DTU Management, Risř Campus, Technical University of Denmark (Denmark); Münster, M., E-mail: maem@dtu.dk [DTU Management, Risř Campus, Technical University of Denmark (Denmark); Ravn, H., E-mail: hans.ravn@aeblevangen.dk [RAM-lřse edb, Ćblevangen 55, 2765 Smřrum (Denmark); Söderman, M. Ljunggren, E-mail: maria.ljunggren@chalmers.se [Energy and Environment, Chalmers University of Technology, Gothenburg (Sweden); IVL Swedish Environmental Research Institute, Gothenburg (Sweden)

    2013-09-15T23:59:59.000Z

    Highlights: • Review of main optimization tools in the field of waste management. • Different optimization methods are applied. • Different fractions are analyzed. • There is focus on different parameters in different geographical regions. • More research is needed which encompasses both recycling and energy solutions. - Abstract: Strategic and operational decisions in waste management, in particular with respect to investments in new treatment facilities, are needed due to a number of factors, including continuously increasing amounts of waste, political demands for efficient utilization of waste resources, and the decommissioning of existing waste treatment facilities. Optimization models can assist in ensuring that these investment strategies are economically feasible. Various economic optimization models for waste treatment have been developed which focus on different parameters. Models focusing on transport are one example, but models focusing on energy production have also been developed, as well as models which take into account a plant’s economies of scale, environmental impact, material recovery and social costs. Finally, models combining different criteria for the selection of waste treatment methods in multi-criteria analysis have been developed. A thorough updated review of the existing models is presented, and the main challenges and crucial parameters that need to be taken into account when assessing the economic performance of waste treatment alternatives are identified. The review article will assist both policy-makers and model-developers involved in assessing the economic performance of waste treatment alternatives.

  13. Voluntary Protection Program Onsite, Liquid Waste Contract Savannah River Site- February 2011

    Broader source: Energy.gov [DOE]

    Evaluation to determine whether the Liquid Waste Contract Savannah River Site is continuing to perform at a level deserving DOE-VPP Star recognition.

  14. Hanford facility dangerous waste permit application, 325 hazardous waste treatment units. Revision 1

    SciTech Connect (OSTI)

    NONE

    1997-07-01T23:59:59.000Z

    This report contains the Hanford Facility Dangerous Waste Permit Application for the 325 Hazardous Waste Treatment Units (325 HWTUs) which consist of the Shielded Analytical Laboratory, the 325 Building, and the 325 Collection/Loadout Station Tank. The 325 HWTUs receive, store, and treat dangerous waste generated by Hanford Facility programs. Routine dangerous and/or mixed waste treatment that will be conducted in the 325 HWTUs will include pH adjustment, ion exchange, carbon absorption, oxidation, reduction, waste concentration by evaporation, precipitation, filtration, solvent extraction, solids washing, phase separation, catalytic destruction, and solidification/stabilization.

  15. Disposal of liquid radioactive wastes through wells or shafts

    SciTech Connect (OSTI)

    Perkins, B.L.

    1982-01-01T23:59:59.000Z

    This report describes disposal of liquids and, in some cases, suitable solids and/or entrapped gases, through: (1) well injection into deep permeable strata, bounded by impermeable layers; (2) grout injection into an impermeable host rock, forming fractures in which the waste solidifies; and (3) slurrying into excavated subsurface cavities. Radioactive materials are presently being disposed of worldwide using all three techniques. However, it would appear that if the techniques were verified as posing minimum hazards to the environment and suitable site-specific host rock were identified, these disposal techniques could be more widely used.

  16. Method for aqueous radioactive waste treatment

    DOE Patents [OSTI]

    Bray, L.A.; Burger, L.L.

    1994-03-29T23:59:59.000Z

    Plutonium, strontium, and cesium found in aqueous waste solutions resulting from nuclear fuel processing are removed by contacting the waste solutions with synthetic zeolite incorporating up to about 5 wt % titanium as sodium titanate in an ion exchange system. More than 99.9% of the plutonium, strontium, and cesium are removed from the waste solutions. 3 figures.

  17. Method for aqueous radioactive waste treatment

    DOE Patents [OSTI]

    Bray, Lane A. (Richland, WA); Burger, Leland L. (Richland, WA)

    1994-01-01T23:59:59.000Z

    Plutonium, strontium, and cesium found in aqueous waste solutions resulting from nuclear fuel processing are removed by contacting the waste solutions with synthetic zeolite incorporating up to about 5 wt % titanium as sodium titanate in an ion exchange system. More than 99.9% of the plutonium, strontium, and cesium are removed from the waste solutions.

  18. Evaluation of alternative treatments for spent fuel rod consolidation wastes and other miscellaneous commercial transuranic wastes

    SciTech Connect (OSTI)

    Ross, W.A.; Schneider, K.J.; Oma, K.H.; Smith, R.I.; Bunnell, L.R.

    1986-05-01T23:59:59.000Z

    Eight alternative treatments (and four subalternatives) are considered for both existing commercial transuranic wastes and future wastes from spent fuel consolidation. Waste treatment is assumed to occur at a hypothetical central treatment facility (a Monitored Retrieval Storage facility was used as a reference). Disposal in a geologic repository is also assumed. The cost, process characteristics, and waste form characteristics are evaluated for each waste treatment alternative. The evaluation indicates that selection of a high-volume-reduction alternative can save almost $1 billion in life-cycle costs for the management of transuranic and high-activity wastes from 70,000 MTU of spent fuel compared to the reference MRS process. The supercompaction, arc pyrolysis and melting, and maximum volume reduction alternatives are recommended for further consideration; the latter two are recommended for further testing and demonstration.

  19. Nuclear waste treatment program. Annual report for FY 1985

    SciTech Connect (OSTI)

    Powell, J.A. (ed.)

    1986-04-01T23:59:59.000Z

    Two of the US Department of Energy's (DOE) nuclear waste management-related goals are: (1) to ensure that waste management is not an obstacle to the further deployment of light-water reactors (LWR) and the closure of the nuclear fuel cycle and (2) to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Terminal Waste Disposal and Remedial Action of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory (PNL) during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide (1) documented technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and (2) problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting assistance, as required, to treat existing wastes. This annual report describes progress during FY 1985 toward meeting these two objectives. The detailed presentation is organized according to the task structure of the program.

  20. Mixed Waste Treatment Project: Computer simulations of integrated flowsheets

    SciTech Connect (OSTI)

    Dietsche, L.J.

    1993-12-01T23:59:59.000Z

    The disposal of mixed waste, that is waste containing both hazardous and radioactive components, is a challenging waste management problem of particular concern to DOE sites throughout the United States. Traditional technologies used for the destruction of hazardous wastes need to be re-evaluated for their ability to handle mixed wastes, and in some cases new technologies need to be developed. The Mixed Waste Treatment Project (MWTP) was set up by DOE`s Waste Operations Program (EM30) to provide guidance on mixed waste treatment options. One of MWTP`s charters is to develop flowsheets for prototype integrated mixed waste treatment facilities which can serve as models for sites developing their own treatment strategies. Evaluation of these flowsheets is being facilitated through the use of computer modelling. The objective of the flowsheet simulations is to provide mass and energy balances, product compositions, and equipment sizing (leading to cost) information. The modelled flowsheets need to be easily modified to examine how alternative technologies and varying feed streams effect the overall integrated process. One such commercially available simulation program is ASPEN PLUS. This report contains details of the Aspen Plus program.

  1. Independent Oversight Activity Report, Hanford Waste Treatment...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy Office of River Protection review of the High Level Waste Facility heating, ventilation, and air conditioning systems. Independent Oversight Activity Report,...

  2. Enterprise Assessments Operational Awareness Record, Waste Treatment...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Waste (HLW) Facility Hazard Analysis (HA) Process for the HLW Preliminary Documented Safety Analysis upgrade during October 20 - November 6, 2014. The review covered a limited...

  3. Independent Oversight Activity Report, Hanford Waste Treatment...

    Office of Environmental Management (EM)

    that focuses on the technical adequacy of the low activity waste (LAW) documented safety analysis and supporting basis. BNI uses the VSL experimental data and reports to...

  4. State waste discharge permit application for the 200 Area Effluent Treatment Facility and the State-Approved Land Disposal Site

    SciTech Connect (OSTI)

    Not Available

    1993-08-01T23:59:59.000Z

    Application is being made for a permit pursuant to Chapter 173--216 of the Washington Administrative Code (WAC), to discharge treated waste water and cooling tower blowdown from the 200 Area Effluent Treatment Facility (ETF) to land at the State-Approved Land Disposal Site (SALDS). The ETF is located in the 200 East Area and the SALDS is located north of the 200 West Area. The ETF is an industrial waste water treatment plant that will initially receive waste water from the following two sources, both located in the 200 Area on the Hanford Site: (1) the Liquid Effluent Retention Facility (LERF) and (2) the 242-A Evaporator. The waste water discharged from these two facilities is process condensate (PC), a by-product of the concentration of waste from DSTs that is performed in the 242-A Evaporator. Because the ETF is designed as a flexible treatment system, other aqueous waste streams generated at the Hanford Site may be considered for treatment at the ETF. The origin of the waste currently contained in the DSTs is explained in Section 2.0. An overview of the concentration of these waste in the 242-A Evaporator is provided in Section 3.0. Section 4.0 describes the LERF, a storage facility for process condensate. Attachment A responds to Section B of the permit application and provides an overview of the processes that generated the wastes, storage of the wastes in double-shell tanks (DST), preliminary treatment in the 242-A Evaporator, and storage at the LERF. Attachment B addresses waste water treatment at the ETF (under construction) and the addition of cooling tower blowdown to the treated waste water prior to disposal at SALDS. Attachment C describes treated waste water disposal at the proposed SALDS.

  5. Fluid dynamic demonstrations for waste retrieval and treatment

    SciTech Connect (OSTI)

    Youngblood, E.L. Jr.; Hylton, T.D.; Berry, J.B.; Cummins, R.L.; Ruppel, F.R. [Oak Ridge National Lab., TN (United States); Hanks, R.W. [R.W. Hanks Associates, Inc. (United States). Slurry Transport Consultant

    1994-02-01T23:59:59.000Z

    The objective of this study was to develop or identify flow correlations for predicting the flow parameters needed for the design and operation of slurry pipeline systems for transporting radioactive waste of the type stored in the Hanford single-shell tanks and the type stored at the Oak Ridge National Laboratory (ORNL). This was done by studying the flow characteristics of simulated waste with rheological properties similar to those of the actual waste. Chemical simulants with rheological properties similar to those of the waste stored in the Hanford single-shell tanks were developed by Pacific Northwest Laboratories, and simulated waste with properties similar to those of ORNL waste was developed at ORNL for use in the tests. Rheological properties and flow characteristics of the simulated slurry were studied in a test loop in which the slurry was circulated through three pipeline viscometers (constructed of 1/2-, 3/4-, and 1-in. schedule 40 pipe) at flow rates up to 35 gal/min. Runs were made with ORNL simulated waste at 54 wt % to 65 wt % total solids and temperatures of 25{degree}C and 55{degree}C. Grinding was done prior to one run to study the effect of reduced particle size. Runs were made with simulated Hanford single-shell tank waste at approximately 43 wt % total solids and at temperatures of 25{degree}C and 50{degree}C. The rheology of simulated Hanford and ORNL waste supernatant liquid was also measured.

  6. ORS 466 - Storage, Treatment, and Disposal of Hazardous Waste...

    Open Energy Info (EERE)

    ORS 466 - Storage, Treatment, and Disposal of Hazardous Waste and Materials Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: ORS...

  7. Summary - System Planning for Low-Activity Waste Treatment at...

    Office of Environmental Management (EM)

    Management (DOE-EM) External Technical Review of System Planning for Low-Activity Waste Treatment at Hanford Why DOE-EM Did This Review Construction of the facilities of...

  8. Office of River Protection Waste Treatment and Immobilizatin...

    Broader source: Energy.gov (indexed) [DOE]

    Review of the Office of River Protection Waste Treatment and Immobilization Project Construction Site, November 16-18, 2010 The U.S. Department of Energy Office of Independent...

  9. Constructed Wetlands and Waste Stabilization Ponds for municipal wastewater treatment in France: comparison of

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    13 Constructed Wetlands and Waste Stabilization Ponds for municipal wastewater treatment in France In France, vertical flow constructed wetlands and waste stabilisation ponds are both extensive treatment Vertical Flow Constructed Wetlands, Waste Stabilization Ponds, operation and maintenance, sludge management

  10. One System Integrated Project Team: Retrieval and Delivery of Hanford Tank Wastes for Vitrification in the Waste Treatment Plant - 13234

    SciTech Connect (OSTI)

    Harp, Benton J. [U.S. Department of Energy, Office of River Protection, Post Office Box 550, Richland, Washington 99352 (United States)] [U.S. Department of Energy, Office of River Protection, Post Office Box 550, Richland, Washington 99352 (United States); Kacich, Richard M. [Bechtel National, Inc., 2435 Stevens Center Place, Richland, Washington 99354 (United States)] [Bechtel National, Inc., 2435 Stevens Center Place, Richland, Washington 99354 (United States); Skwarek, Raymond J. [Washington River Protection Solutions LLC, Post Office Box 850, Richland, Washington 99352 (United States)] [Washington River Protection Solutions LLC, Post Office Box 850, Richland, Washington 99352 (United States)

    2013-07-01T23:59:59.000Z

    The One System Integrated Project Team (IPT) was formed in late 2011 as a way for improving the efficiency of delivery and treatment of highly radioactive waste stored in underground tanks at the U.S. Department of Energy's (DOE's) 586-square-mile Hanford Site in southeastern Washington State. The purpose of the One System IPT is to improve coordination and integration between the Hanford's Waste Treatment Plant (WTP) contractor and the Tank Operations Contractor (TOC). The vision statement is: One System is a WTP and TOC safety-conscious team that, through integrated management and implementation of risk-informed decision and mission-based solutions, will enable the earliest start of safe and efficient treatment of Hanford's tank waste, to protect the Columbia River, environment and public. The IPT is a formal collaboration between Bechtel National, Inc. (BNI), which manages design and construction of the WTP for the U.S. Department of Energy's Office of River Protection (DOEORP), and Washington River Protection Solutions (WRPS), which manages the TOC for ORP. More than fifty-six (56) million gallons of highly radioactive liquid waste are stored in one hundred seventy-seven (177) aging, underground tanks. Most of Hanford's waste tanks - one hundred forty-nine (149) of them - are of an old single-shell tank (SST) design built between 1944 and 1964. More than sixty (60) of these tanks have leaked in the past, releasing an estimated one million gallons of waste into the soil and threatening the nearby Columbia River. There are another twenty-eight (28) new double-shelled tanks (DSTs), built from 1968 to 1986, that provide greater protection to the environment. In 1989, DOE, the U.S. Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) signed a landmark agreement that required Hanford to comply with federal and state environmental standards. It also paved the way for agreements that set deadlines for retrieving the tank wastes and for building and operating the WTP. The tank wastes are the result of Hanford's nearly fifty (50) years of plutonium production. In the intervening years, waste characteristics have been increasingly better understood. However, waste characteristics that are uncertain and will remain as such represent a significant technical challenge in terms of retrieval, transport, and treatment, as well as for design and construction of WTP. What also is clear is that the longer the waste remains in the tanks, the greater the risk to the environment and the people of the Pacific Northwest. The goal of both projects - tank operations and waste treatment - is to diminish the risks posed by the waste in the tanks at the earliest possible date. About two hundred (200) WTP and TOC employees comprise the IPT. Individual work groups within One System include Technical, Project Integration and Controls, Front-End Design and Project Definition, Commissioning, Nuclear Safety and Engineering Systems Integration, and Environmental Safety and Health and Quality Assurance (ESH and QA). Additional functions and team members will be added as the WTP approaches the operational phase. The team has undertaken several initiatives since its formation to collaborate on issues: (1) alternate scenarios for delivery of wastes from the tank farms to WTP; (2) improvements in managing Interface Control Documents; (3) coordination on various technical issues, including the Defense Nuclear Facilities Nuclear Safety Board's Recommendation 2010-2; (4) deployment of the SmartPlant{sup R} Foundation-Configuration Management System; and (5) preparation of the joint contract deliverable of the Operational Readiness Support Plan. (authors)

  11. One System Integrated Project Team: Retrieval And Delivery Of The Hanford Tank Wastes For Vitrification In The Waste Treatment Plant

    SciTech Connect (OSTI)

    Harp, Benton J. [Department of Energy, Office of River Protection, Richland, Washington (United States); Kacich, Richard M. [Bechtel National, Inc., Richland, WA (United States); Skwarek, Raymond J. [Washington River Protection Solutions LLC, Richland, WA (United States)

    2012-12-20T23:59:59.000Z

    The One System Integrated Project Team (IPT) was formed in late 2011 as a way for improving the efficiency of delivery and treatment of highly radioactive waste stored in underground tanks at the U.S. Department of Energy's (DOE's) 586-square-mile Hanford Site in southeastern Washington State. The purpose of the One System IPT is to improve coordination and integration between the Hanford's Waste Treatment Plant (WTP) contractor and the Tank Operations Contractor (TOC). The vision statement is: One System is a WTP and TOC safety conscious team that, through integrated management and implementation of risk-informed decision and mission-based solutions, will enable the earliest start of safe and efficient treatment of Hanford's tank waste, to protect the Columbia River, environment and public. The IPT is a formal collaboration between Bechtel National, Inc. (BNI), which manages design and construction of the WTP for the U.S. Department of Energy's Office of River Protection (DOEORP), and Washington River Protection Solutions (WRPS), which manages the TOC for ORP. More than fifty-six (56) million gallons of highly radioactive liquid waste are stored in one hundred seventy-seven (177) aging, underground tanks. Most of Hanford's waste tanks - one hundred forty-nine (149) of them - are of an old single-shell tank (SST) design built between 1944 and 1964. More than sixty (60) of these tanks have leaked in the past, releasing an estimated one million gallons of waste into the soil and threatening the nearby Columbia River. There are another twenty-eight (28) new double-shelled tanks (DSTs), built from 1968 to 1986, that provide greater protection to the environment. In 1989, DOE, the U.S. Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) signed a landmark agreement that required Hanford to comply with federal and state environmental standards. It also paved the way for agreements that set deadlines for retrieving the tank wastes and for building and operating the WTP. The tank wastes are the result of Hanford's nearly fifty (50) years of plutonium production. In the intervening years, waste characteristics have been increasingly better understood. However, waste characteristics that are uncertain and will remain as such represent a significant technical challenge in terms of retrieval, transport, and treatment, as well as for design and construction ofWTP. What also is clear is that the longer the waste remains in the tanks, the greater the risk to the environment and the people of the Pacific Northwest. The goal of both projects - tank operations and waste treatment - is to diminish the risks posed by the waste in the tanks at the earliest possible date. About two hundred (200) WTP and TOC employees comprise the IPT. Individual work groups within One System include Technical, Project Integration & Controls, Front-End Design & Project Definition, Commissioning, Nuclear Safety & Engineering Systems Integration, and Environmental Safety and Health and Quality Assurance (ESH&QA). Additional functions and team members will be added as the WTP approaches the operational phase. The team has undertaken several initiatives since its formation to collaborate on issues: (1) alternate scenarios for delivery of wastes from the tank farms to WTP; (2) improvements in managing Interface Control Documents; (3) coordination on various technical issues, including the Defense Nuclear Facilities Nuclear Safety Board's Recommendation 2010-2; (4) deployment of the SmartPlant? Foundation-configuration Management System; and (5) preparation of the joint contract deliverable of the Operational Readiness Support Plan.

  12. An overview of in situ waste treatment technologies

    SciTech Connect (OSTI)

    Walker, S.; Hyde, R.A.; Piper, R.B.; Roy, M.W.

    1992-08-01T23:59:59.000Z

    In situ technologies are becoming an attractive remedial alternative for eliminating environmental problems. In situ treatments typically reduce risks and costs associated with retrieving, packaging, and storing or disposing-waste and are generally preferred over ex situ treatments. Each in situ technology has specific applications, and, in order to provide the most economical and practical solution to a waste problem, these applications must be understood. This paper presents an overview of thirty different in situ remedial technologies for buried wastes or contaminated soil areas. The objective of this paper is to familiarize those involved in waste remediation activities with available and emerging in situ technologies so that they may consider these options in the remediation of hazardous and/or radioactive waste sites. Several types of in situ technologies are discussed, including biological treatments, containment technologies, physical/chemical treatments, solidification/stabilization technologies, and thermal treatments. Each category of in situ technology is briefly examined in this paper. Specific treatments belonging to these categories are also reviewed. Much of the information on in situ treatment technologies in this paper was obtained directly from vendors and universities and this information has not been verified.

  13. An overview of in situ waste treatment technologies

    SciTech Connect (OSTI)

    Walker, S.; Hyde, R.A.; Piper, R.B.; Roy, M.W.

    1992-01-01T23:59:59.000Z

    In situ technologies are becoming an attractive remedial alternative for eliminating environmental problems. In situ treatments typically reduce risks and costs associated with retrieving, packaging, and storing or disposing-waste and are generally preferred over ex situ treatments. Each in situ technology has specific applications, and, in order to provide the most economical and practical solution to a waste problem, these applications must be understood. This paper presents an overview of thirty different in situ remedial technologies for buried wastes or contaminated soil areas. The objective of this paper is to familiarize those involved in waste remediation activities with available and emerging in situ technologies so that they may consider these options in the remediation of hazardous and/or radioactive waste sites. Several types of in situ technologies are discussed, including biological treatments, containment technologies, physical/chemical treatments, solidification/stabilization technologies, and thermal treatments. Each category of in situ technology is briefly examined in this paper. Specific treatments belonging to these categories are also reviewed. Much of the information on in situ treatment technologies in this paper was obtained directly from vendors and universities and this information has not been verified.

  14. Conditioning of Boron-Containing Low and Intermediate Level Liquid Radioactive Waste - 12041

    SciTech Connect (OSTI)

    Gorbunova, Olga A. [SUE SIA 'Radon', Moscow (Russian Federation); Kamaeva, Tatiana S. [Vernadsky Institute of Geochemistry and Analytical Chemistry Russian Academy of Sciences, Moscow (Russian Federation)

    2012-07-01T23:59:59.000Z

    Improved cementation of low and intermediate level radioactive waste (ILW and LLW) aided by vortex electromagnetic treatment as well as silica addition was investigated. Positive effects including accelerated curing of boron-containing cement waste forms, improve end product quality, decreased product volume and reduced secondary LRW volume from equipment decontamination were established. These results established the possibility of boron-containing LRW cementation without the use of neutralizing alkaline additives that greatly increase the volume of the final product intended for long-term storage (burial). Physical (electromagnetic) treatment in a vortex mixer can change the state of LRW versus chemical treatment. By treating the liquid phase of cement solution only, instead of the whole solution, and using fine powder and nano-particles of ferric oxides instead of separable ferromagnetic cores for the activating agents the positive effect are obtained. VET for 1 to 3 minutes yields boron-containing LRW cemented products of satisfactory quality. Silica addition at 10 % by weight will accelerate curing and solidification and to decrease radionuclide leaching rates from boron-containing cement products. (authors)

  15. active liquid wastes: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Assessment Institute Rethinking the Waste Hierarchy March 2005 Recommendations A number of specific recommendations for achieving cost-effective waste policies can be made...

  16. active liquid waste: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Assessment Institute Rethinking the Waste Hierarchy March 2005 Recommendations A number of specific recommendations for achieving cost-effective waste policies can be made...

  17. Laboratory Evaporation Testing Of Hanford Waste Treatment Plant Low Activity Waste Off-Gas Condensate Simulant

    SciTech Connect (OSTI)

    Adamson, Duane J.; Nash, Charles A.; McCabe, Daniel J.; Crawford, Charles L.; Wilmarth, William R.

    2014-01-27T23:59:59.000Z

    The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream, LAW Off-Gas Condensate, from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable de-coupled operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of canistered glass waste forms. This LAW Off-Gas Condensate stream contains components that are volatile at melter temperatures and are problematic for the glass waste form. Because this stream recycles within WTP, these components accumulate in the Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to be within acceptable concentration ranges in the LAW glass. Diverting the stream reduces the halides in the recycled Condensate and is a key outcome of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, identifying a disposition path becomes vitally important. This task examines the impact of potential future disposition of this stream in the Hanford tank farms, and investigates auxiliary evaporation to enable another disposition path. Unless an auxiliary evaporator is used, returning the stream to the tank farms would require evaporation in the 242-A evaporator. This stream is expected to be unusual because it will be very high in corrosive species that are volatile in the melter (chloride, fluoride, sulfur), will have high ammonia, and will contain carryover particulates of glass-former chemicals. These species have potential to cause corrosion of tanks and equipment, precipitation of solids, release of ammonia gas vapors, and scale in the tank farm evaporator. Routing this stream to the tank farms does not permanently divert it from recycling into the WTP, only temporarily stores it prior to reprocessing. Testing is normally performed to demonstrate acceptable conditions and limits for these compounds in wastes sent to the tank farms. The primary parameter of this phase of the test program was measuring the formation of solids during evaporation in order to assess the compatibility of the stream with the evaporator and transfer and storage equipment. The origin of this LAW Off-Gas Condensate stream will be the liquids from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW facility melter offgas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover. The soluble components are expected to be mostly sodium and ammonium salts of nitrate, chloride, and fluoride. This stream has not been generated yet, and, thus, the composition will not be available until the WTP begins operation, but a simulant has been produced based on models, calculations, and comparison with pilot-scale tests. This report discusses results of evaporation testing of the simulant. Two conditions were tested, one with the simulant at near neutral pH, and a second at alkaline pH. The neutral pH test is comparable to the conditions in the Hanford Effluent Treatment Facility (ETF) evaporator, although that evaporator operates at near atmospheric pressure and tests were done under vacuum. For the alkaline test, the target pH was based on the tank farm corrosion control program requirements, and the test protocol and equipment was comparable to that used for routine evaluation of feed compatibility studies for the 242-A evaporator. One of the

  18. Liquid and Gaseous Waste Operations Department annual operating report, CY 1995

    SciTech Connect (OSTI)

    Maddox, J.J.; Scott, C.B.

    1996-03-01T23:59:59.000Z

    This report describes the operating activities, upgrade activities, maintenance, and other activities regarding liquid and gaseous low level radioactive waste management at the Oak Ridge National Laboratory. Miscellaneous activities include training, audits, tours, and environmental restoration support.

  19. Waste Treatment And Immobilization Plant U. S. Department Of Energy Office Of River Protection Submerged Bed Scrubber Condensate Disposition Project - Abstract # 13460

    SciTech Connect (OSTI)

    Yanochko, Ronald M [Washington River Protection Solutions, Richland, WA (United States); Corcoran, Connie [AEM Consulting, LLC, Richland, WA (United States)

    2012-11-15T23:59:59.000Z

    The Hanford Waste Treatment and Immobilization Plant (WTP) will generate an off-gas treatment system secondary liquid waste stream [submerged bed scrubber (SBS) condensate], which is currently planned for recycle back to the WTP Low Activity Waste (LAW) melter. This SBS condensate waste stream is high in Tc-99, which is not efficiently captured in the vitrified glass matrix. A pre-conceptual engineering study was prepared in fiscal year 2012 to evaluate alternate flow paths for melter off-gas secondary liquid waste generated by the WTP LAW facility. This study evaluated alternatives for direct off-site disposal of this SBS without pre-treatment, which mitigates potential issues associated with recycling.

  20. Review of Nuclear Safety Culture at the Hanford Site Waste Treatment...

    Office of Environmental Management (EM)

    Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project, October 2010 Review of Nuclear Safety Culture at the Hanford Site Waste...

  1. Use of Novel Highly Selective Ion Exchange Media for Minimizing the Waste Arising from Different NPP and Other Liquids

    SciTech Connect (OSTI)

    Tusa, Esko; Harjula, Risto; Lehto, Jukka

    2003-02-25T23:59:59.000Z

    Highly selective inorganic ion exchangers give new possibilities to implement and operate new innovative treatment systems for radioactive liquids. Because of high selectivity these ion exchangers can be used even in liquids of high salt concentrations. Only selected target nuclides will be separated and inactive salts are left in the liquid, which can be released or recategorized. Thus, it is possible to reduce the volume of radioactive waste dramatically. On the other hand, only a small volume of highly selective material is required in applications, which makes it possible to design totally new types of compact treatment systems. The major benefit of selective ion exchange media comes from the very large volume reduction of radioactive waste in final disposal. It is also possible to save in investment costs, because small ion exchanger volumes can be used and handled in a very small facility. This paper describes different applications of these highly selective ion exchangers, both commercial fullscale applications and laboratory tests, to give the idea of their efficiency for different liquids.

  2. Cost of meeting geothermal liquid effluent disposal regulations

    SciTech Connect (OSTI)

    Wells, K.D.; Currie, J.W.; Price, B.A.; Rogers, E.A.

    1981-06-01T23:59:59.000Z

    Background information is presented on the characteristics of liquid wastes and the available disposal options. Regulations that may directly or indirectly influence liquid waste disposal are reviewed. An assessment of the available wastewater-treatment systems is provided. A case study of expected liquid-waste-treatment and disposal costs is summarized. (MHR)

  3. Waste Treatment and Immobilization Plant Progress

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron SpinPrincetonUsing Maps1DOE AwardsDNitrate Salt BearingProcessingWaste

  4. Sodium-Bearing Waste Treatment, Applied Technology Plan

    SciTech Connect (OSTI)

    Lance Lauerhass; Vince C. Maio; S. Kenneth Merrill; Arlin L. Olson; Keith J. Perry

    2003-06-01T23:59:59.000Z

    Settlement Agreement between the Department of Energy and the State of Idaho mandates treatment of sodium-bearing waste at the Idaho Nuclear Technology and Engineering Center within the Idaho National Engineering and Environmental Laboratory. One of the requirements of the Settlement Agreement is to complete treatment of sodium-bearing waste by December 31, 2012. Applied technology activities are required to provide the data necessary to complete conceptual design of four identified alternative processes and to select the preferred alternative. To provide a technically defensible path forward for the selection of a treatment process and for the collection of needed data, an applied technology plan is required. This document presents that plan, identifying key elements of the decision process and the steps necessary to obtain the required data in support of both the decision and the conceptual design. The Sodium-Bearing Waste Treatment Applied Technology Plan has been prepared to provide a description/roadmap of the treatment alternative selection process. The plan details the results of risk analyzes and the resulting prioritized uncertainties. It presents a high-level flow diagram governing the technology decision process, as well as detailed roadmaps for each technology. The roadmaps describe the technical steps necessary in obtaining data to quantify and reduce the technical uncertainties associated with each alternative treatment process. This plan also describes the final products that will be delivered to the Department of Energy Idaho Operations Office in support of the office's selection of the final treatment technology.

  5. Technical Safety Requirements for the B695 Segment of the Decontamination and Waste Treatment Facility

    SciTech Connect (OSTI)

    Larson, H L

    2007-09-07T23:59:59.000Z

    This document contains Technical Safety Requirements (TSRs) for the Radioactive and Hazardous Waste Management (RHWM) Division's B695 Segment of the Decontamination and Waste Treatment Facility (DWTF) at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the B695 Segment of the DWTF. The TSRs are derived from the Documented Safety Analysis (DSA) for the B695 Segment of the DWTF (LLNL 2004). The analysis presented there determined that the B695 Segment of the DWTF is a low-chemical hazard, Hazard Category 3, nonreactor nuclear facility. The TSRs consist primarily of inventory limits as well as controls to preserve the underlying assumptions in the hazard analyses. Furthermore, appropriate commitments to safety programs are presented in the administrative controls section of the TSRs. The B695 Segment of the DWTF (B695 and the west portion of B696) is a waste treatment and storage facility located in the northeast quadrant of the LLNL main site. The approximate area and boundary of the B695 Segment of the DWTF are shown in the B695 Segment of the DWTF DSA. Activities typically conducted in the B695 Segment of the DWTF include container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. B695 is used to store and treat radioactive, mixed, and hazardous waste, and it also contains equipment used in conjunction with waste processing operations to treat various liquid and solid wastes. The portion of the building called Building 696 Solid Waste Processing Area (SWPA), also referred to as B696S in this report, is used primarily to manage solid radioactive waste. Operations specific to the SWPA include sorting and segregating low-level waste (LLW) and transuranic (TRU) waste, lab-packing, sampling, and crushing empty drums that previously contained LLW. A permit modification for B696S was submitted to DTSC in January 2004 to store and treat hazardous and mixed waste. Upon approval of the permit modification, B696S rooms 1007, 1008, and 1009 will be able to store hazardous and mixed waste for up to 1 year. Furthermore, an additional drum crusher and a Waste Packaging Unit will be permitted to treat hazardous and mixed waste. RHWM generally processes LLW with no, or extremely low, concentrations of transuranics (i.e., much less than 100 nCi/g). Wastes processed often contain only depleted uranium and beta- and gamma-emitting nuclides, e.g., {sup 90}Sr, {sup 137}Cs, {sup 3}H. Chapter 5 of the DSA documents the derivation of TSRs and develops the operational limits that protect the safety envelope defined for this facility. The DSA is applicable to the handling of radioactive waste stored and treated in the B695 Segment of the DWTF. Section 5 of the TSR, Administrative Controls, contains those Administrative Controls necessary to ensure safe operation of the B695 Segment of the DWTF. A basis explanation follows each of the requirements described in Section 5.5, Specific Administrative Controls. The basis explanation does not constitute an additional requirement, but is intended as an expansion of the logic and reasoning behind development of the requirement. Programmatic Administrative Controls are addressed in Section 5.6.

  6. Treatment of Mixed Wastes via Fixed Bed Gasification

    SciTech Connect (OSTI)

    None

    1998-10-28T23:59:59.000Z

    This report outlines the details of research performed under USDOE Cooperative Agreement DE-FC21-96MC33258 to evaluate the ChemChar hazardous waste system for the destruction of mixed wastes, defined as those that contain both RCRA-regulated haz- ardous constituents and radionuclides. The ChemChar gasification system uses a granular carbonaceous char matrix to immobilize wastes and feed them into the gasifier. In the gasifier wastes are subjected to high temperature reducing conditions, which destroy the organic constituents and immobilize radionuclides on the regenerated char. Only about 10 percent of the char is consumed on each pass through the gasifier, and the regenerated char can be used to treat additional wastes. When tested on a 4-inch diameter scale with a continuous feed unit as part of this research, the ChemChar gasification system was found to be effective in destroying RCRA surrogate organic wastes (chlorobenzene, dichloroben- zene, and napht.halene) while retaining on the char RCRA heavy metals (chromium, nickel, lead, and cadmium) as well as a fission product surrogate (cesium) and a plutonium surrogate (cerium). No generation of harmful byproducts was observed. This report describes the design and testing of the ChemChar gasification system and gives the operating procedures to be followed in using the system safely and effectively for mixed waste treatment.

  7. Waste characterization for the F/H Effluent Treatment Facility in support of waste certification

    SciTech Connect (OSTI)

    Brown, D.F.

    1994-10-17T23:59:59.000Z

    The Waste Acceptance Criteria (WAC) procedures define the rules concerning packages of solid Low Level Waste (LLW) that are sent to the E-area vaults (EAV). The WACs tabulate the quantities of 22 radionuclides that require manifesting in waste packages destined for each type of vault. These quantities are called the Package Administrative Criteria (PAC). If a waste package exceeds the PAC for any radionuclide in a given vault, then specific permission is needed to send to that vault. To avoid reporting insignificant quantities of the 22 listed radionuclides, the WAC defines the Minimum Reportable Quantity (MRQ) of each radionuclide as 1/1000th of the PAC. If a waste package contains less than the MRQ of a particular radionuclide, then the package`s manifest will list that radionuclide as zero. At least one radionuclide has to be reported, even if all are below the MRQ. The WAC requires that the waste no be ``hazardous`` as defined by SCDHEC/EPA regulations and also lists several miscellaneous physical/chemical requirements for the packages. This report evaluates the solid wastes generated within the F/H Effluent Treatment Facility (ETF) for potential impacts on waste certification.

  8. Mixed and low-level waste treatment facility project

    SciTech Connect (OSTI)

    Not Available

    1992-04-01T23:59:59.000Z

    The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies.

  9. Apparatus and method for ultrasonic treatment of a liquid

    DOE Patents [OSTI]

    Chandler, Darrell P.; Posakony, Gerald J.; Bond, Leonard J.; Bruckner-Lea, Cynthia J.

    2006-04-04T23:59:59.000Z

    The present invention is an apparatus for ultrasonically treating a liquid to generate a product. The apparatus is capable of treating a continuously-flowing, or intermittently-flowing, liquid along a line segment coincident with the flow path of the liquid. The apparatus has one or more ultrasonic transducers positioned asymmetrically about the line segment. The ultrasonic field encompasses the line segment and the ultrasonic energy may be concentrated along the line segment. Lysing treatments have been successfully achieved with efficiencies of greater than 99% using ultrasound at MHz frequencies without erosion or heating problems and without the need for chemical or mechanical pretreatment, or contrast agents. The present invention overcomes drawbacks of current ultrasonic treatments beyond lysing and opens up new sonochemical and sonophysical processing opportunities.

  10. Apparatus and method for ultrasonic treatment of a liquid

    DOE Patents [OSTI]

    Chandler, Darrell P [Richland, WA; Posakony, Gerald J [Richland, WA; Bond, Leonard J [Richland, WA; Bruckner-Lea, Cynthia J [Richland, WA

    2003-01-14T23:59:59.000Z

    The present invention is an apparatus and method for ultrasonically treating a liquid to generate a product. The apparatus is capable of treating a continuously-flowing, or intermittently-flowing, liquid along a line segment coincident with the flow path of the liquid. The apparatus has one or more ultrasonic transducers positioned asymmetrically about the line segment. The ultrasonic field encompasses the line segment and the ultrasonic energy may be concentrated along the line segment. Lysing treatments have been successfully achieved with efficiencies of greater than 99% using ultrasound at MHz frequencies without erosion or heating problems and without the need for chemical or mechanical pretreatment, or contrast agents. The present invention overcomes drawbacks of current ultrasonic treatments beyond lysing and opens up new sonochemical and sonophysical processing opportunities.

  11. Mixed and Low-Level Treatment Facility Project. Appendix B, Waste stream engineering files, Part 1, Mixed waste streams

    SciTech Connect (OSTI)

    Not Available

    1992-04-01T23:59:59.000Z

    This appendix contains the mixed and low-level waste engineering design files (EDFS) documenting each low-level and mixed waste stream investigated during preengineering studies for Mixed and Low-Level Waste Treatment Facility Project. The EDFs provide background information on mixed and low-level waste generated at the Idaho National Engineering Laboratory. They identify, characterize, and provide treatment strategies for the waste streams. Mixed waste is waste containing both radioactive and hazardous components as defined by the Atomic Energy Act and the Resource Conservation and Recovery Act, respectively. Low-level waste is waste that contains radioactivity and is not classified as high-level waste, transuranic waste, spent nuclear fuel, or 11e(2) byproduct material as defined by DOE 5820.2A. Test specimens of fissionable material irradiated for research and development only, and not for the production of power or plutonium, may be classified as low-level waste, provided the concentration of transuranic is less than 100 nCi/g. This appendix is a tool that clarifies presentation format for the EDFS. The EDFs contain waste stream characterization data and potential treatment strategies that will facilitate system tradeoff studies and conceptual design development. A total of 43 mixed waste and 55 low-level waste EDFs are provided.

  12. System for removing liquid waste from a tank

    DOE Patents [OSTI]

    Meneely, Timothy K. (Penn Hills, PA); Sherbine, Catherine A. (N. Versailles Township, Allegheny County, PA)

    1994-01-01T23:59:59.000Z

    A tank especially suited for nuclear applications is disclosed. The tank comprises a tank shell for protectively surrounding the liquid contained therein; an inlet positioned on the tank for passing a liquid into the tank; a sump positioned in an interior portion of the tank for forming a reservoir of the liquid; a sloped incline for resting the tank thereon and for creating a natural flow of the liquid toward the sump; a pump disposed adjacent the tank for pumping the liquid; and a pipe attached to the pump and extending into the sump for passing the liquid therethrough. The pump pumps the liquid in the sump through the pipe and into the pump for discharging the liquid out of the tank.

  13. System for removing liquid waste from a tank

    DOE Patents [OSTI]

    Meneely, T.K.; Sherbine, C.A.

    1994-04-26T23:59:59.000Z

    A tank especially suited for nuclear applications is disclosed. The tank comprises a tank shell for protectively surrounding the liquid contained therein; an inlet positioned on the tank for passing a liquid into the tank; a sump positioned in an interior portion of the tank for forming a reservoir of the liquid; a sloped incline for resting the tank thereon and for creating a natural flow of the liquid toward the sump; a pump disposed adjacent the tank for pumping the liquid; and a pipe attached to the pump and extending into the sump for passing the liquid there through. The pump pumps the liquid in the sump through the pipe and into the pump for discharging the liquid out of the tank. 2 figures.

  14. Waste treatment and metal recovery at the Robbins Company

    SciTech Connect (OSTI)

    Clark, P.

    1990-05-01T23:59:59.000Z

    The Robbins Company, of Attleboro, Massachusetts, a medium-sized jewelry manufacturing and plating company, installed a new wastewater treatment and metal recovery system, which forms a closed-loop, completed in February, 1988. The company now generates very small quantities of hazardous wastes non-contact cooling water from the annealing furnaces, and intends to complete it`s water conservation program by installing one or more chillers on the furnaces. Since 1986, chemical usage has dropped 81.8%, hazardous waste generation 89% and water usage by 47.7%, generating an annual savings of over $71,000.

  15. SECONDARY WASTE/ETF (EFFLUENT TREATMENT FACILITY) PRELIMINARY PRE-CONCEPTUAL ENGINEERING STUDY

    SciTech Connect (OSTI)

    MAY TH; GEHNER PD; STEGEN GARY; HYMAS JAY; PAJUNEN AL; SEXTON RICH; RAMSEY AMY

    2009-12-28T23:59:59.000Z

    This pre-conceptual engineering study is intended to assist in supporting the critical decision (CD) 0 milestone by providing a basis for the justification of mission need (JMN) for the handling and disposal of liquid effluents. The ETF baseline strategy, to accommodate (WTP) requirements, calls for a solidification treatment unit (STU) to be added to the ETF to provide the needed additional processing capability. This STU is to process the ETF evaporator concentrate into a cement-based waste form. The cementitious waste will be cast into blocks for curing, storage, and disposal. Tis pre-conceptual engineering study explores this baseline strategy, in addition to other potential alternatives, for meeting the ETF future mission needs. Within each reviewed case study, a technical and facility description is outlined, along with a preliminary cost analysis and the associated risks and benefits.

  16. PROBABILITY BASED CORROSION CONTROL FOR LIQUID WASTE TANKS - PART III

    SciTech Connect (OSTI)

    Hoffman, E.; Edwards, T.

    2010-12-09T23:59:59.000Z

    The liquid waste chemistry control program is designed to reduce the pitting corrosion occurrence on tank walls. The chemistry control program has been implemented, in part, by applying engineering judgment safety factors to experimental data. However, the simple application of a general safety factor can result in use of excessive corrosion inhibiting agents. The required use of excess corrosion inhibitors can be costly for tank maintenance, waste processing, and in future tank closure. It is proposed that a probability-based approach can be used to quantify the risk associated with the chemistry control program. This approach can lead to the application of tank-specific chemistry control programs reducing overall costs associated with overly conservative use of inhibitor. Furthermore, when using nitrite as an inhibitor, the current chemistry control program is based on a linear model of increased aggressive species requiring increased protective species. This linear model was primarily supported by experimental data obtained from dilute solutions with nitrate concentrations less than 0.6 M, but is used to produce the current chemistry control program up to 1.0 M nitrate. Therefore, in the nitrate space between 0.6 and 1.0 M, the current control limit is based on assumptions that the linear model developed from data in the <0.6 M region is applicable in the 0.6-1.0 M region. Due to this assumption, further investigation of the nitrate region of 0.6 M to 1.0 M has potential for significant inhibitor reduction, while maintaining the same level of corrosion risk associated with the current chemistry control program. Ongoing studies have been conducted in FY07, FY08, FY09 and FY10 to evaluate the corrosion controls at the SRS tank farm and to assess the minimum nitrite concentrations to inhibit pitting in ASTM A537 carbon steel below 1.0 molar nitrate. The experimentation from FY08 suggested a non-linear model known as the mixture/amount model could be used to predict the probability of corrosion in ASTM A537 in varying solutions as shown in Figure 1. The mixture/amount model takes into account not only the ratio (or mixture) of inhibitors and aggressive species, but also the total concentration (or amount) of species in a solution. Historically, the ratio was the only factor taken into consideration in the development of the current chemistry control program. During FY09, an experimental program was undertaken to refine the mixture/amount model by further investigating the risk associated with reducing the minimum molar nitrite concentration required to confidently inhibit pitting in dilute solutions. The results of FY09, as shown in Figure 2, quantified the probability for a corrosion free outcome for combinations of nitrate and nitrite. The FY09 data predict probabilities up to 70%. Additional experimental data are needed to increase the probability to an acceptable percentage.

  17. Interaction between temperature and ammonia in mesophilic digesters for animal waste treatment

    E-Print Network [OSTI]

    Angenent, Lars T.

    and agricultural processing, centralized and decentralized wastewater treatment plants, and solid waste recoveryInteraction between temperature and ammonia in mesophilic digesters for animal waste treatment, and their interconnectivity on the methane yield of anaerobic processes for animal waste treatment. During period 1 (day 0

  18. Low level mixed waste thermal treatment technical basis report

    SciTech Connect (OSTI)

    Place, B.G.

    1994-12-01T23:59:59.000Z

    Detailed characterization of the existing and projected Hanford Site Radioactive Mixed Waste (RMW) inventory was initiated in 1993 (Place 1993). This report presents an analysis of the existing and projected RMW inventory. The subject characterization effort continues to be in support of the following engineering activities related to thermal treatment of Hanford Site RMW: (1) Contracting for commercial thermal treatment; (2) Installation and operation of an onsite thermal treatment facility (Project W-242); (3) Treatment at another Department of Energy (DOE) site. The collation of this characterization information (data) has emphasized the establishment of a common data base for the entire existing RMW inventory so that the specification of feed streams destined for different treatment facilities can be coordinated.

  19. aqueous liquid waste: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Majda 2005-01-01 18 Momentum, Heat, and Neutral Mass Transport in Convective Atmospheric Pressure Plasma-Liquid Systems and Implications for Aqueous Targets CERN Preprints...

  20. Recent developments in geothermal waste treatment biotechnology

    SciTech Connect (OSTI)

    Premuzic, E.T.; Lin, M.S.; Jin, J.Z.

    1993-05-01T23:59:59.000Z

    Continuing studies at Brookhaven National Laboratory (BNL) have shown that cost-efficient biotechnology for the removal of toxic trace metals from geothermal sludge is feasible. Pilot-scale experiments have shown that fast rates (< 24-h) of metal removal at 55{degree}C--60{degree}C can be achieved with removal efficiencies of better than 80%, yielding a product well within the environmental regulatory limits. Recent studies have shown that radionuclides, such as radium present in low concentrations in some sludges, can also be removed by means of a secondary biotreatment. The process produces an aqueous phase which contains all of the regulatory metals in a soluble form. A follow-up technology for the treatment of the aqueous phase is concurrently being developed at BNL. Preliminary results indicate that a small volume concentrate of metals can be generated producing an aqueous phase which meets drinking water standards. In this paper the current state-of-the-biotechnology will be discussed.

  1. Proceedings of waste stream minimization and utilization innovative concepts: An experimental technology exchange. Volume 2, Industrial liquid waste processing, industrial gaseous waste processing

    SciTech Connect (OSTI)

    Lee, V.E. [ed.; Watts, R.L.

    1993-04-01T23:59:59.000Z

    This two-volume proceedings summarize the results of fifteen innovations that were funded through the US Department of Energy`s Innovative Concept Program. The fifteen innovations were presented at the sixth Innovative Concepts Fair, held in Austin, Texas, on April 22--23, 1993. The concepts in this year`s fair address innovations that can substantially reduce or use waste streams. Each paper describes the need for the proposed concept, the concept being proposed, and the concept`s economics and market potential, key experimental results, and future development needs. The papers are divided into two volumes: Volume 1 addresses innovations for industrial solid waste processing and municipal waste reduction/recycling, and Volume 2 addresses industrial liquid waste processing and industrial gaseous waste processing. Individual reports are indexed separately.

  2. Method for the simultaneous recovery of radionuclides from liquid radioactive wastes using a solvent

    DOE Patents [OSTI]

    Romanovskiy, Valeriy Nicholiavich (St. Petersburg, RU); Smirnov, Igor V. (St. Petersburg, RU); Babain, Vasiliy A. (St. Petersburg, RU); Todd, Terry A. (Aberdeen, ID); Brewer, Ken N. (Arco, ID)

    2001-01-01T23:59:59.000Z

    The present invention relates to solvents, and methods, for selectively extracting and recovering radionuclides, especially cesium and strontium, rare earths and actinides from liquid radioactive wastes. More specifically, the invention relates to extracting agent solvent compositions comprising complex organoboron compounds, substituted polyethylene glycols, and neutral organophosphorus compounds in a diluent. The preferred solvent comprises a chlorinated cobalt dicarbollide, diphenyl-dibutylmethylenecarbamoylphosphine oxide, PEG-400, and a diluent of phenylpolyfluoroalkyl sulfone. The invention also provides a method of using the invention extracting agents to recover cesium, strontium, rare earths and actinides from liquid radioactive waste.

  3. Solvent for the simultaneous recovery of radionuclides from liquid radioactive wastes

    DOE Patents [OSTI]

    Romanovskiy, Valeriy Nicholiavich (St. Petersburg, RU); Smirnov, Igor V. (St. Petersburg, RU); Babain, Vasiliy A. (St. Petersburg, RU); Todd, Terry A. (Aberdeen, ID); Brewer, Ken N. (Arco, ID)

    2002-01-01T23:59:59.000Z

    The present invention relates to solvents, and methods, for selectively extracting and recovering radionuclides, especially cesium and strontium, rare earths and actinides from liquid radioactive wastes. More specifically, the invention relates to extracting agent solvent compositions comprising complex organoboron compounds, substituted polyethylene glycols, and neutral organophosphorus compounds in a diluent. The preferred solvent comprises a chlorinated cobalt dicarbollide, diphenyl-dibutylmethylenecarbamoylphosphine oxide, PEG-400, and a diluent of phenylpolyfluoroalkyl sulfone. The invention also provides a method of using the invention extracting agents to recover cesium, strontium, rare earths and actinides from liquid radioactive waste.

  4. MEASUREMENTS TAKEN IN SUPPORT OF QUALIFICATION OF PROCESSING SAVANNAH RIVER SITE LOW-LEVEL LIQUID WASTE INTO SALTSTONE

    SciTech Connect (OSTI)

    Reigel, M.; Bibler, N.; Diprete, C.; Cozzi, A.; Staub, A.; Ray, J.

    2010-01-27T23:59:59.000Z

    The Saltstone Facility at the Savannah River Site (SRS) immobilizes low-level liquid waste into Saltstone to be disposed of in the Z-Area Saltstone Disposal Facility, Class Three Landfill. In order to meet the permit conditions and regulatory limits set by the South Carolina Department of Health and Environmental Control (SCDHEC), the Resource Conservation and Recovery Act (RCRA) and the Environmental Protection Agency (EPA), both the low-level salt solution and Saltstone samples are analyzed quarterly. Waste acceptance criteria (WAC) are designed to confirm the salt solution sample from the Tank Farm meets specific radioactive and chemical limits. The toxic characteristic leaching procedure (TCLP) is used to confirm that the treatment has immobilized the hazardous constituents of the salt solution. This paper discusses the methods used to characterize the salt solution and final Saltstone samples from 2007-2009.

  5. Municipal Solid Waste (MSW) to Liquid Fuels Synthesis, Volume 1: Availability of Feedstock and Technology

    SciTech Connect (OSTI)

    Valkenburt, Corinne; Walton, Christie W.; Thompson, Becky L.; Gerber, Mark A.; Jones, Susanne B.; Stevens, Don J.

    2008-12-01T23:59:59.000Z

    This report investigated the potential of using municipal solid waste (MSW) to make synthesis gas (syngas) suitable for production of liquid fuels. Issues examined include: • MSW physical and chemical properties affecting its suitability as a gasifier feedstock and for liquid fuels synthesis • expected process scale required for favorable economics • the availability of MSW in quantities sufficient to meet process scale requirements • the state-of-the-art of MSW gasification technology.

  6. Waste-Lithium-Liquid (WLL) Flow Battery for Stationary Energy Storage Applications Youngsik Kim* and Nina MahootcheianAsl

    E-Print Network [OSTI]

    Zhou, Yaoqi

    Waste-Lithium-Liquid (WLL) Flow Battery for Stationary Energy Storage Applications Youngsik Kim in a Waste-Lithium-Liquid (WLL) flow battery that can be used in a stationary energy storage application. Li* and Nina MahootcheianAsl Richard Lugar Center for Renewable Energy, Department of Mechanical Engineering

  7. APPLICATION OF A THIN FILM EVAPORATOR SYSTEM FOR MANAGEMENT OF LIQUID HIGH-LEVEL WASTES AT HANFORD

    SciTech Connect (OSTI)

    TEDESCHI AR; WILSON RA

    2010-01-14T23:59:59.000Z

    A modular, transportable evaporator system, using thin film evaporative technology, is planned for deployment at the Hanford radioactive waste storage tank complex. This technology, herein referred to as a wiped film evaporator (WFE), will be located at grade level above an underground storage tank to receive pumped liquids, concentrate the liquid stream from 1.1 specific gravity to approximately 1.4 and then return the concentrated solution back into the tank. Water is removed by evaporation at an internal heated drum surface exposed to high vacuum. The condensed water stream will be shipped to the site effluent treatment facility for final disposal. This operation provides significant risk mitigation to failure of the aging 242-A Evaporator facility; the only operating evaporative system at Hanford maximizing waste storage. This technology is being implemented through a development and deployment project by the tank farm operating contractor, Washington River Protection Solutions (WRPS), for the Office of River Protection/Department of Energy (ORP/DOE), through Columbia Energy & Environmental Services, Inc. (Columbia Energy). The project will finalize technology maturity and install a system at one of the double-shell tank farms. This paper discusses results of pre-project pilot-scale testing by Columbia Energy and ongoing technology maturation development scope through fiscal year 2012, including planned additional pilot-scale and full-scale simulant testing and operation with actual radioactive tank waste.

  8. Statistical Description of Liquid Low-Level Waste System Transssuranic Wastes at Oak Ridge Nation Laboratory, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    NONE

    1996-12-01T23:59:59.000Z

    The US DOE has presented plans for processing liquid low-level wastes (LLLW) located at Oak Ridge National Laboratory (ORNL) in the LLLW tank system. These wastes are among the most hazardous on the Oak Ridge reservation and exhibit both RCRA toxic and radiological hazards. The Tennessee Department of Health and Environment has mandated that the processing of these wastes must begin by the year 2002 and the the goal should be permanent disposal at a site off the Oak Ridge Reservation. To meet this schedule, DOE will solicit bids from various private sector companies for the construction of a processing facility on land located near the ORNL Melton Valley Storage Tanks to be operated by the private sector on a contract basis. This report will support the Request for Proposal process and will give potential vendors information about the wastes contained in the ORNL tank farm system. The report consolidates current data about the properties and composition of these wastes and presents methods to calculate the error bounds of the data in the best technically defensible manner possible. The report includes information for only the tank waste that is to be included in the request for proposal.

  9. LABORATORY OPTIMIZATION TESTS OF TECHNETIUM DECONTAMINATION OF HANFORD WASTE TREATMENT PLANT LOW ACTIVITY WASTE OFF-GAS CONDENSATE SIMULANT

    SciTech Connect (OSTI)

    Taylor-Pashow, K.; Nash, C.; McCabe, D.

    2014-09-29T23:59:59.000Z

    The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Off-Gas Condensate) from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable de-coupled operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of glass waste. This LAW Off-Gas Condensate stream contains components that are volatile at melter temperatures and are problematic for the glass waste form. Because this stream recycles within WTP, these components accumulate in the Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and diverting the stream reduces the halides in the recycled Condensate and is a key outcome of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, identifying a disposition path becomes vitally important. This task examines the potential treatment of this stream to remove radionuclides and subsequently disposition the decontaminated stream elsewhere, such as the Effluent Treatment Facility (ETF), for example. The treatment process envisioned is very similar to that used for the Actinide Removal Process (ARP) that has been operating for years at the Savannah River Site (SRS), and focuses on using mature radionuclide removal technologies that are also compatible with longterm tank storage and immobilization methods. For this new application, testing is needed to demonstrate acceptable treatment sorbents and precipitating agents and measure decontamination factors for additional radionuclides in this unique waste stream. The origin of this LAW Off-Gas Condensate stream will be the liquids from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW melter off-gas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover. The soluble components are expected to be mostly sodium and ammonium salts of nitrate, chloride, and fluoride. This stream has not been generated yet and will not be available until the WTP begins operation, but a simulant has been produced based on models, calculations, and comparison with pilot-scale tests. One of the radionuclides that is volatile and expected to be in greatest abundance in this LAW Off-Gas Condensate stream is Technetium-99 ({sup 99}Tc). Technetium will not be removed from the aqueous waste in the Hanford WTP, and will primarily end up immobilized in the LAW glass by repeated recycle of the off-gas condensate into the LAW melter. Other radionuclides that are low but are also expected to be in measurable concentration in the LAW Off-Gas Condensate are {sup 129}I, {sup 90}Sr, {sup 137}Cs, {sup 241}Pu, and {sup 241}Am. These are present due to their partial volatility and some entrainment in the off-gas system. This report discusses results of optimized {sup 99}Tc decontamination testing of the simulant. Testing examined use of inorganic reducing agents for {sup 99}Tc. Testing focused on minimizing the quantity of sorbents/reactants added, and minimizing mixing time to reach the decontamination targets in this simulant formulation. Stannous chloride and ferrous sulfate were tested as reducing agents to determine the minimum needed to convert soluble pertechnetate to the insoluble technetium dioxide. The reducing agents were tried with and without sorbents.

  10. THE ROLE OF LIQUID WASTE PRETREATMENT TECHNOLOGIES IN SOLVING THE DOE CLEAN-UP MISSION

    SciTech Connect (OSTI)

    Wilmarth, B; Sheryl Bush, S

    2008-10-31T23:59:59.000Z

    The objective of this report is to describe the pretreatment solutions that allow treatment to be tailored to specific wastes, processing ahead of the completion schedules for the main treatment facilities, and reduction of technical risks associated with future processing schedules. Wastes stored at Hanford and Savannah River offer challenging scientific and engineering tasks. At both sites, space limitations confound the ability to effectively retrieve and treat the wastes. Additionally, the radiation dose to the worker operating and maintaining the radiochemical plants has a large role in establishing the desired radioactivity removal. However, the regulatory requirements to treat supernatant and saltcake tank wastes differ at the two sites. Hanford must treat and remove radioactivity from the tanks based on the TriParty Agreement and Waste Incidental to Reprocessing (WIR) documentation. These authorizing documents do not specify treatment technologies; rather, they specify endstate conditions. Dissimilarly, Waste Determinations prepared at SRS in accordance with Section 3116 of the 2005 National Defense Authorization Act along with state operating permits establish the methodology and amounts of radioactivity that must be removed and may be disposed of in South Carolina. After removal of entrained solids and site-specific radionuclides, supernatant and saltcake wastes are considered to be low activity waste (LAW) and are immobilized in glass and disposed of at the Hanford Site Integrated Disposal Facility (IDF) or formulated into a grout for disposal at the Savannah River Site Saltstone Disposal Facility. Wastes stored at the Hanford Site or SRS comprise saltcake, supernate, and sludges. The supernatant and saltcake waste fractions contain primarily sodium salts, metals (e.g., Al, Cr), cesium-137 (Cs-137), technetium-99 (Tc-99) and entrained solids containing radionuclides such as strontium-90 (Sr-90) and transuranic elements. The sludges contain many of the transition metal hydroxides that precipitate when the spent acidic process solutions are rendered alkaline with sodium hydroxide. The sludges contain Sr-90 and transuranic elements. The wastes stored at each site have been generated and stored for over fifty years. Although the majority of the wastes were generated to support nuclear weapons production and reprocessing, the wastes differ substantially between the sites. Table 5 shows the volumes and total radioactivity (including decay daughters) of the waste phases stored in tanks at each site. At Hanford, there are 177 tanks that contain 56.5 Mgal of waste. SRS has 51 larger tanks, of which 2 are closed, that contain 36.5 Mgal. Mainly due to recovery operations, the waste stored at Hanford has less total curies than that stored at Savannah River. The total radioactivity of the Hanford wastes contains approximately 190 MCi, and the total radioactivity of the Savannah River wastes contains 400 MCi.

  11. Modeling Offgas Systems for the Hanford Waste Treatment Plant

    SciTech Connect (OSTI)

    Smith, Frank G., III

    2005-09-02T23:59:59.000Z

    To augment steady-state design calculations, dynamic models of three offgas systems that will be used in the Waste Treatment Plant now under construction at the Hanford Site were developed using Aspen Custom Modeler{trademark}. The offgas systems modeled were those for the High Level Waste (HLW) melters, Low Activity Waste (LAW) melters and HLW Pulse Jet Ventilation (PJV) system. The models do not include offgas chemistry but only consider the two major species in the offgas stream which are air and water vapor. This is sufficient to perform material and energy balance calculations that accurately show the dynamic behavior of gas pressure, temperature, humidity and flow throughout the systems. The models are structured to perform pressure drop calculations across the various unit operations using a combination of standard engineering calculations and empirical data based correlations for specific pieces of equipment. The models include process controllers, gas ducting, control valves, exhaust fans and the offgas treatment equipment. The models were successfully used to analyze a large number of operating scenarios including both normal and off-normal conditions.

  12. Karlsruhe Database for Radioactive Wastes (KADABRA) - Accounting and Management System for Radioactive Waste Treatment - 12275

    SciTech Connect (OSTI)

    Himmerkus, Felix; Rittmeyer, Cornelia [WAK Rueckbau- und Entsorgungs- GmbH, 76339 Eggenstein-Leopoldshafen (Germany)

    2012-07-01T23:59:59.000Z

    The data management system KADABRA was designed according to the purposes of the Cen-tral Decontamination Department (HDB) of the Wiederaufarbeitungsanlage Karlsruhe Rueckbau- und Entsorgungs-GmbH (WAK GmbH), which is specialized in the treatment and conditioning of radioactive waste. The layout considers the major treatment processes of the HDB as well as regulatory and legal requirements. KADABRA is designed as an SAG ADABAS application on IBM system Z mainframe. The main function of the system is the data management of all processes related to treatment, transfer and storage of radioactive material within HDB. KADABRA records the relevant data concerning radioactive residues, interim products and waste products as well as the production parameters relevant for final disposal. Analytical data from the laboratory and non destructive assay systems, that describe the chemical and radiological properties of residues, production batches, interim products as well as final waste products, can be linked to the respective dataset for documentation and declaration. The system enables the operator to trace the radioactive material through processing and storage. Information on the actual sta-tus of the material as well as radiological data and storage position can be gained immediately on request. A variety of programs accessed to the database allow the generation of individual reports on periodic or special request. KADABRA offers a high security standard and is constantly adapted to the recent requirements of the organization. (authors)

  13. HIGH ALUMINUM HLW (HIGH LEVEL WASTE ) GLASSES FOR HANFORDS WTP (WASTE TREATMENT PROJECT)

    SciTech Connect (OSTI)

    KRUGER AA; BOWAN BW; JOSEPH I; GAN H; KOT WK; MATLACK KS; PEGG IL

    2010-01-04T23:59:59.000Z

    This paper presents the results of glass formulation development and melter testing to identify high waste loading glasses to treat high-Al high level waste (HLW) at Hanford. Previous glass formulations developed for this HLW had high waste loadings but their processing rates were lower that desired. The present work was aimed at improving the glass processing rate while maintaining high waste loadings. Glass formulations were designed, prepared at crucible-scale and characterized to determine their properties relevant to processing and product quality. Glass formulations that met these requirements were screened for melt rates using small-scale tests. The small-scale melt rate screening included vertical gradient furnace (VGF) and direct feed consumption (DFC) melter tests. Based on the results of these tests, modified glass formulations were developed and selected for larger scale melter tests to determine their processing rate. Melter tests were conducted on the DuraMelter 100 (DMIOO) with a melt surface area of 0.11 m{sup 2} and the DuraMelter 1200 (DMI200) HLW Pilot Melter with a melt surface area of 1.2 m{sup 2}. The newly developed glass formulations had waste loadings as high as 50 wt%, with corresponding Al{sub 2}O{sub 3} concentration in the glass of 26.63 wt%. The new glass formulations showed glass production rates as high as 1900 kg/(m{sup 2}.day) under nominal melter operating conditions. The demonstrated glass production rates are much higher than the current requirement of 800 kg/(m{sup 2}.day) and anticipated future enhanced Hanford Tank Waste Treatment and Immobilization Plant (WTP) requirement of 1000 kg/(m{sup 2}.day).

  14. Groundwater impact assessment report for the 1325-N Liquid Waste Disposal Facility

    SciTech Connect (OSTI)

    Alexander, D.J.; Johnson, V.G.

    1993-09-01T23:59:59.000Z

    In 1943 the Hanford Site was chosen as a location for the Manhattan Project to produce plutonium for use in nuclear weapons. The 100-N Area at Hanford was used from 1963 to 1987 for a dual-purpose, plutonium production and steam generation reactor and related operational support facilities (Diediker and Hall 1987). In November 1989, the reactor was put into dry layup status. During operations, chemical and radioactive wastes were released into the area soil, air, and groundwater. The 1325-N LWDF was constructed in 1983 to replace the 1301-N Liquid Waste Disposal Facility (1301-N LWDF). The two facilities operated simultaneously from 1983 to 1985. The 1301-N LWDF was retired from use in 1985 and the 1325-N LWDF continued operation until April 1991, when active discharges to the facility ceased. Effluent discharge to the piping system has been controlled by administrative means. This report discusses ground water contamination resulting from the 1325-N Liquid Waste Disposal facility.

  15. Sodium-bearing Waste Treatment Technology Evaluation Report

    SciTech Connect (OSTI)

    Charles M. Barnes; Arlin L. Olson; Dean D. Taylor

    2004-05-01T23:59:59.000Z

    Sodium-bearing waste (SBW) disposition is one of the U.S. Department of Energy (DOE) Idaho Operation Office’s (NE-ID) and State of Idaho’s top priorities at the Idaho National Engineering and Environmental Laboratory (INEEL). The INEEL has been working over the past several years to identify a treatment technology that meets NE-ID and regulatory treatment requirements, including consideration of stakeholder input. Many studies, including the High-Level Waste and Facilities Disposition Environmental Impact Statement (EIS), have resulted in the identification of five treatment alternatives that form a short list of perhaps the most appropriate technologies for the DOE to select from. The alternatives are (a) calcination with maximum achievable control technology (MACT) upgrade, (b) steam reforming, (c) cesium ion exchange (CsIX) with immobilization, (d) direct evaporation, and (e) vitrification. Each alternative has undergone some degree of applied technical development and preliminary process design over the past four years. This report presents a summary of the applied technology and process design activities performed through February 2004. The SBW issue and the five alternatives are described in Sections 2 and 3, respectively. Details of preliminary process design activities for three of the alternatives (steam reforming, CsIX, and direct evaporation) are presented in three appendices. A recent feasibility study provides the details for calcination. There have been no recent activities performed with regard to vitrification; that section summarizes and references previous work.

  16. Ionic Liquids for Utilization of Waste Heat from Distributed Power Generation Systems

    SciTech Connect (OSTI)

    Joan F. Brennecke; Mihir Sen; Edward J. Maginn; Samuel Paolucci; Mark A. Stadtherr; Peter T. Disser; Mike Zdyb

    2009-01-11T23:59:59.000Z

    The objective of this research project was the development of ionic liquids to capture and utilize waste heat from distributed power generation systems. Ionic Liquids (ILs) are organic salts that are liquid at room temperature and they have the potential to make fundamental and far-reaching changes in the way we use energy. In particular, the focus of this project was fundamental research on the potential use of IL/CO2 mixtures in absorption-refrigeration systems. Such systems can provide cooling by utilizing waste heat from various sources, including distributed power generation. The basic objectives of the research were to design and synthesize ILs appropriate for the task, to measure and model thermophysical properties and phase behavior of ILs and IL/CO2 mixtures, and to model the performance of IL/CO2 absorption-refrigeration systems.

  17. On-Site Decontamination System for Liquid Low Level Radioactive Waste - 13010

    SciTech Connect (OSTI)

    OSMANLIOGLU, Ahmet Erdal [Cekmece Nuclear Research and Training Center, Kucukcekmece Istanbul (Turkey)] [Cekmece Nuclear Research and Training Center, Kucukcekmece Istanbul (Turkey)

    2013-07-01T23:59:59.000Z

    This study is based on an evaluation of purification methods for liquid low-level radioactive waste (LLLW) by using natural zeolite. Generally the volume of liquid low-level waste is relatively large and the specific activity is rather low when compared to other radioactive waste types. In this study, a pilot scale column was used with natural zeolite as an ion exchanger media. Decontamination and minimization of LLLW especially at the generation site decrease operational cost in waste management operations. Portable pilot scale column was constructed for decontamination of LLW on site. Effect of temperature on the radionuclide adsorption of the zeolite was determined to optimize the waste solution temperature for the plant scale operations. In addition, effect of pH on the radionuclide uptake of the zeolite column was determined to optimize the waste solution pH for the plant scale operations. The advantages of this method used for the processing of LLLW are discussed in this paper. (authors)

  18. Assessment of incineration and melting treatment technologies for RWMC buried waste

    SciTech Connect (OSTI)

    Geimer, R.; Hertzler, T.; Gillins, R. [Science Applications International Corp., Idaho Falls, ID (United States); Anderson, G.L. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

    1992-02-01T23:59:59.000Z

    This report provides an identification, description, and ranking evaluation of the available thermal treatment technologies potentially capable of treating the Idaho National Engineering Laboratory Radioactive Waste Management Complex (RWMC) buried mixed waste. The ranking evaluation focused separately upon incinerators for treatment of combustible wastes and melters for noncombustible wastes. The highest rank incinerators are rotary kilns and controlled air furnaces, while the highest rank melters are the hearth configuration plasma torch, graphite electrode arc, and joule-heated melters. 4 refs.

  19. Sampling and Analysis Plan - Waste Treatment Plant Seismic Boreholes Project

    SciTech Connect (OSTI)

    Reidel, Steve P.

    2006-05-26T23:59:59.000Z

    This sampling and analysis plan (SAP) describes planned data collection activities for four entry boreholes through the sediment overlying the basalt, up to three new deep rotary boreholes through the basalt and sedimentary interbeds, and one corehole through the basalt and sedimentary interbeds at the Waste Treatment Plant (WTP) site. The SAP will be used in concert with the quality assurance plan for the project to guide the procedure development and data collection activities needed to support borehole drilling, geophysical measurements, and sampling. This SAP identifies the American Society of Testing Materials standards, Hanford Site procedures, and other guidance to be followed for data collection activities.

  20. Waste Treatment Plant and Tank Farm Program | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently20,000 Russian Nuclear Warheads|of Energy WashingtonWaste IsolationTreatment Plant

  1. Working with SRNL - Our Facilities- Waste Treatment Laboratories

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron SpinPrincetonUsingWhat is abigpresentedMetalWaste Treatment Laboratories

  2. CHARACTERIZATION OF DEFENSE NUCLEAR WASTE USING HAZARDOUS WASTE GUIDANCE. APPLICATIONS TO HANFORD SITE ACCELERATED HIGH-LEVEL WASTE TREATMENT AND DISPOSAL MISSION0

    SciTech Connect (OSTI)

    Hamel, William; Huffman, Lori; Lerchen, Megan; Wiemers, Karyn

    2003-02-27T23:59:59.000Z

    Federal hazardous waste regulations were developed for management of industrial waste. These same regulations are also applicable for much of the nation's defense nuclear wastes. At the U.S. Department of Energy's (DOE) Hanford Site in southeast Washington State, one of the nation's largest inventories of nuclear waste remains in storage in large underground tanks. The waste's regulatory designation and its composition and form constrain acceptable treatment and disposal options. Obtaining detailed knowledge of the tank waste composition presents a significant portion of the many challenges in meeting the regulatory-driven treatment and disposal requirements for this waste. Key in applying the hazardous waste regulations to defense nuclear wastes is defining the appropriate and achievable quality for waste feed characterization data and the supporting evidence demonstrating that applicable requirements have been met at the time of disposal. Application of a performance-based approach to demonstrating achievable quality standards will be discussed in the context of the accelerated high-level waste treatment and disposal mission at the Hanford Site.

  3. Croatian refiner meets waste water treatment standards, reduces fines

    SciTech Connect (OSTI)

    Meier, A.L. [Krofta Engineering Corp., Lenox, MA (United States); Nikolic, O. [INA Oil Refinery, Rijeka (Croatia)

    1995-11-27T23:59:59.000Z

    A new approach to waste water treatment at a refinery in Croatia produces effluent that not only meets the region`s regulations for disposal into the Adriatic Sea, but also surpasses the refinery`s specifications for recycling process water. Key to the dramatic reduction in pollutants was the installation of a Sandfloat unit developed by Krofta Engineering Corp. The Sandfloat unit is a dissolved air flotation clarifier that combines flocculation, flotation, and multilayer filtration to produce high-quality effluent. In fact, the effluent from the unit has a lower hydrocarbon concentration than water from the underground wells that supply process water to the refinery. While similar systems have been used for decades in industrial applications, this is the first time a Sandfloat unit has been installed in an oil refinery. The article describes the problem, refinery operations, treatment costs, and effluent recycling.

  4. Successful Waste Treatment Methods at Sandia National Laboratories

    SciTech Connect (OSTI)

    Rast, D.M.; Thompson, J.J.; Cooper, T.W.; Stockham, D.J

    2007-07-01T23:59:59.000Z

    During the remediation of the waste landfills at Sandia National Laboratory in Albuquerque, New Mexico nine drums of mock high explosives were generated. This mixed waste stream was proposed to several offsite vendors for treatment and prices ranged from $2.50 to $10 per gram a total cost estimated to be in excess of $2 million dollars. This cost represents more than 30 percent of the annual budget for the Sandia Waste Management Operations. Concentrated solutions of common oxidizers, such as nitrates, nitrites, and peroxides, will also act as oxidizers and will give positive results in the Hazard Categorization oxidizer test. These solutions carry an EPA Hazardous Waste Number D001, Ignitable Waste, and Oxidizer as defined in 49 CFR 173.151. Sandia decided that given budget and time constraints to meet a Federal Facilities Compliance Act milestone, a process for onsite treatment should be evaluated. Clean samples of mock high explosive materials were obtained from Pantex excess inventory and treatability studies initiated to develop a treatment formula and process. The following process was developed and implemented in the summer of 2006: - Size reduction to allow for dissolution of the barium nitrate in water; - Dissolution of the Mock HE in water; - Deactivation of the oxidizer; - Stabilization of the barium and the cadmium contamination present as an underlying hazardous constituent. This project was completed and the treatment milestone achieved for less than $300,000. The Disassembly Sanitization Operation (DSO) is a process that was implemented to support weapon disassembly and disposition using recycling and waste minimization while achieving the demilitarization mission. The Department of Energy is faced with disassembling and disposition of a huge inventory of retired weapons, components, training equipment, spare parts, and weapon maintenance equipment. Environmental regulations have caused a dramatic increase for information needed to support the disposal and handling of these parts and materials. Manufacturing information from past decades often does not meet the needs for regulatory decisions of today to assure proper management of weapons components. Huge inventories of classified weapon components were required to have long-term storage at Sandia and many other locations throughout the complex. These materials are stored because they are classified, they may also contain radiological and/or hazardous components and disposal options may not have existed for this material. Long-term storage is costly and somewhat problematic. It requires a secured storage area, monitoring, auditing and it also has the potential for loss or theft of this material. Overall recycling rates for materials sent through the DSO process have enabled 70 to 80% of these components to be recycled. These components are made to extreme standards and are made of high quality materials. Once the material has been sanitized, the demand for these metals is very high. The DSO process for the NGPF classified components established the credibility of this technique as a viable process for addressing the long-term storage requirements of classified weapons component inventory. The success of this operation has generated interest from other Sandia Organization other locations throughout the complex. Other organizations are soliciting the help of the DSO team and the DSO is responding to these solicitations by expanding its scope to include work for other projects. For example, Pantex has asked the DSO team to assist with the destruction of their classified components. The operation is full scale and continues to grow and serve SNL/NM and DoE by providing a solution to this evolving issue. On an ongoing basis, SNL has been incurring expenses for the management and storage of classified components. It is estimated that this project will save the DoE and Sandia several hundreds of thousands of dollars until the excess inventory is eliminated. This innovative approach eliminates the need for long-term storage of classified weapons components and the

  5. DuraLith Alkali-Aluminosilicate Geopolymer Waste Form Testing for Hanford Secondary Waste

    SciTech Connect (OSTI)

    Gong, W. L.; Lutz, Werner; Pegg, Ian L.

    2011-07-21T23:59:59.000Z

    The primary objective of the work reported here was to develop additional information regarding the DuraLith alkali aluminosilicate geopolymer as a waste form for liquid secondary waste to support selection of a final waste form for the Hanford Tank Waste Treatment and Immobilization Plant secondary liquid wastes to be disposed in the Integrated Disposal Facility on the Hanford Site. Testing focused on optimizing waste loading, improving waste form performance, and evaluating the robustness of the waste form with respect to waste variability.

  6. Integrated Waste Treatment Unit GFSI Risk Management Plan

    SciTech Connect (OSTI)

    W. A. Owca

    2007-06-21T23:59:59.000Z

    This GFSI Risk Management Plan (RMP) describes the strategy for assessing and managing project risks for the Integrated Waste Treatment Unit (IWTU) that are specifically within the control and purview of the U.S. Department of Energy (DOE), and identifies the risks that formed the basis for the DOE contingency included in the performance baseline. DOE-held contingency is required to cover cost and schedule impacts of DOE activities. Prior to approval of the performance baseline (Critical Decision-2) project cost contingency was evaluated during a joint meeting of the Contractor Management Team and the Integrated Project Team for both contractor and DOE risks to schedule and cost. At that time, the contractor cost and schedule risk value was $41.3M and the DOE cost and schedule risk contingency value is $39.0M. The contractor cost and schedule risk value of $41.3M was retained in the performance baseline as the contractor's management reserve for risk contingency. The DOE cost and schedule risk value of $39.0M has been retained in the performance baseline as the DOE Contingency. The performance baseline for the project was approved in December 2006 (Garman 2006). The project will continue to manage to the performance baseline and change control thresholds identified in PLN-1963, ''Idaho Cleanup Project Sodium-Bearing Waste Treatment Project Execution Plan'' (PEP).

  7. Recovery and utilization of waste liquids in ultra-clean coal preparation by chemical leaching

    SciTech Connect (OSTI)

    Xu Zesheng; Shi Zhimin; Yang Qiaowen; Wang Xinguo [China Univ. of Mining and Technology, Beijing (China). Beijing Graduate School

    1997-12-31T23:59:59.000Z

    Coal with ash lower than 1%, being called an ultra-clean coal, has many potential applications, such as a substitute for diesel fuel, production of carbon electrodes, superior activated carbon and other chemical materials. It is difficult to reduce coal ash to such a level by conventional coal preparation technology. By means of chemical leaching with the proper concentration of alkali and acid solutions, any coal can be deeply deashed to 1% ash level. However, the cost of chemical methods is higher than that of physical ones, additionally, the waste liquids would give rise to environmental pollution if used on a large scale. If the waste liquids from chemical preparation of ultra-clean coal can be recovered and utilized, so as to produce salable by-products, the cost of chemical leaching will be reduced. This processing will also solve the pollution problem of these waste liquids. This paper describes recovery and utilization methods for these liquids used in chemical leaching, including the recoveries of alkali, silica, sodium-salt and aluminium-salt. A preliminary estimate was made regarding its economic benefits. It shows that this research solves the two problems in the chemical preparation of ultra-clean coal. One is the high-cost and the other is environmental pollution. This research demonstrates good potential for the production of ultra-clean coal on an industrial scale.

  8. Design report on the test system used to assess treatment of trench water from Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    Kent, T.E.; Taylor, P.A.

    1992-09-01T23:59:59.000Z

    New liquid waste streams will be generated as a consequence of closure activities at Waste Area Grouping (WAG) 6 at Oak Ridge National Laboratory (ORNL). It is proposed that these waste streams be treated for removal of contaminants by adding them to the ORNL wastewater treatment facilities. Previous bench-scale treatability studies indicate that ORNL treatment operations will adequately remove the contaminants, although additional study is required to characterize the secondary waste materials produced as a result of the treatment. A larger scale treatment system was constructed to produce secondary wastes in the quantities necessary for characterization and US Environmental protection Agency toxicity characteristic leaching procedure (TCLP) testing. The test system is designed to simulate the operation of the ORNL process waste treatment facilities and to treat a mixture of ORNL process wastewater and WAG 6 wastewater at a combined flow rate of 0.5 L/min. The system is designed to produce the necessary quantities of waste sludges and spent carbon for characterization studies and TCLP testing.

  9. Hanford Waste Simulants Created to Support the Research and Development on the River Protection Project - Waste Treatment Plant

    SciTech Connect (OSTI)

    Eibling, R.E.

    2001-07-26T23:59:59.000Z

    The development of nonradioactive waste simulants to support the River Protection Project - Waste Treatment Plant bench and pilot-scale testing is crucial to the design of the facility. The report documents the simulants development to support the SRTC programs and the strategies used to produce the simulants.

  10. Voluntary Protection Program Onsite Review, Waste Treatment Plant Construction Project- June 2010

    Broader source: Energy.gov [DOE]

    Evaluation to determine whether Waste Treatment Plant Construction Project is continuing to perform at a level deserving DOE-VPP Star recognition.

  11. Voluntary Protection Program Onsite Review, Bechtel National Inc., Waste Treatment Plant Construction Site – November 2013

    Broader source: Energy.gov [DOE]

    Evaluation to determine whether Bechtel National Inc., Waste Treatment Plant Construction Site is performing at a level deserving DOE-VPP Star recognition.

  12. Voluntary Protection Program Onsite Review, Waste Treatment Plant Hanford Site- June 2010

    Broader source: Energy.gov [DOE]

    Evaluation to determine whether the Waste Treatment Plant Hanford Site is continuing to perform at a level deserving DOE-VPP Star recognition.

  13. Decontamination of Nuclear Liquid Wastes Status of CEA and AREVA R and D: Application to Fukushima Waste Waters - 12312

    SciTech Connect (OSTI)

    Fournel, B.; Barre, Y.; Lepeytre, C.; Peycelon, H. [CEA Marcoule, DTCD, BP17171, 30207 Bagnols sur Ceze (France); Grandjean, A. [Institut de Chimie Separative de Marcoule, UMR5257 CEA-CNRS-UM2-ENSCM, BP17171, 30207 Bagnols sur Ceze (France); Prevost, T.; Valery, J.F. [AREVA NC, Paris La Defense (France); Shilova, E.; Viel, P. [CEA Saclay, DSM/IRAMIS/SPCSI, 91191 Gif sur Yvette (France)

    2012-07-01T23:59:59.000Z

    Liquid wastes decontamination processes are mainly based on two techniques: Bulk processes and the so called Cartridges processes. The first technique has been developed for the French nuclear fuel reprocessing industry since the 60's in Marcoule and La Hague. It is a proven and mature technology which has been successfully and quickly implemented by AREVA at Fukushima site for the processing of contaminated waters. The second technique, involving cartridges processes, offers new opportunities for the use of innovative adsorbents. The AREVA process developed for Fukushima and some results obtained on site will be presented as well as laboratory scale results obtained in CEA laboratories. Examples of new adsorbents development for liquid wastes decontamination are also given. A chemical process unit based on co-precipitation technique has been successfully and quickly implemented by AREVA at Fukushima site for the processing of contaminated waters. The asset of this technique is its ability to process large volumes in a continuous mode. Several chemical products can be used to address specific radioelements such as: Cs, Sr, Ru. Its drawback is the production of sludge (about 1% in volume of initial liquid volume). CEA developed strategies to model the co-precipitation phenomena in order to firstly minimize the quantity of added chemical reactants and secondly, minimize the size of co-precipitation units. We are on the way to design compact units that could be mobilized very quickly and efficiently in case of an accidental situation. Addressing the problem of sludge conditioning, cementation appears to be a very attractive solution. Fukushima accident has focused attention on optimizations that should be taken into account in future studies: - To better take account for non-typical aqueous matrixes like seawater; - To enlarge the spectrum of radioelements that can be efficiently processed and especially short lives radioelements that are usually less present in standard effluents resulting from nuclear activities; - To develop reversible solid adsorbents for cartridge-type applications in order to minimize wastes. (authors)

  14. The PERC{trademark} process: Existing and potential applications for induction coupled plasma technology in hazardous and radioactive waste treatment

    SciTech Connect (OSTI)

    Blutke, A.S.; Vavruska, J.S.; Serino, J.F. [Plasma Technology, Inc., Santa Fe, NM (United States)

    1996-12-31T23:59:59.000Z

    Plasma Technology, Inc. (PTI), a Santa Fe, New Mexico corporation has developed the Plasma Energy Recycle and Conversion (PERC){trademark} treatment process as a safe and environmentally clean alternative to conventional thermal destruction technologies. The PERC{trademark} treatment process uses as its heat source an advanced Induction Coupled Plasma (ICP) torch connected to a reaction chamber system with an additional emission control system. For example, organic-based gas, liquid, slurry, and/or solid waste streams can be converted into usable or even salable products while residual emissions are reduced to an absolute minimum. In applications for treatment of hazardous and radioactive waste streams, the PERC system could be used for destruction of the hazardous organic constituents and/or significant waste volume reduction while capturing the radioactive fraction in a non-leachable form. Like Direct Current (DC) and Alternating Current (AC) arc plasma systems, ICP torches offer sufficient energy to decompose, melt and/or vitrify any waste stream. The decision for an arc plasma or an IC plasma system has to be made on a case by case evaluation and is highly dependent on the specific waste stream`s form and composition. Induction coupled plasma technology offers one simple, but significant difference compared to DC or AC arc plasma systems: the ICP torch is electrodeless. To date, enormous research effort has been spent to improve the lifetime of electrodes and the effectiveness of related cooling systems. Arc plasma systems are established in research laboratories worldwide and are approaching a broad use in commercial applications. ICP technology has been improved relatively recently, but nowadays offers complete new and beneficial approaches in the field of waste conversion and treatment.

  15. Composition of Municipal Solid Waste-Need for Thermal Treatment in the present Indian context

    E-Print Network [OSTI]

    Columbia University

    Composition of Municipal Solid Waste- Need for Thermal Treatment in the present Indian context of an eternally inherent low heating value on the other. Current status of Solid Waste Management The MSW Rules front in India17 . None of the major metros have any projects of significant scale of Solid Waste

  16. RADIOACTIVE DEMONSTRATIONS OF FLUIDIZED BED STEAM REFORMING AS A SUPPLEMENTARY TREATMENT FOR HANFORD'S LOW ACTIVITY WASTE AND SECONDARY WASTES

    SciTech Connect (OSTI)

    Jantzen, C.; Crawford, C.; Cozzi, A.; Bannochie, C.; Burket, P.; Daniel, G.

    2011-02-24T23:59:59.000Z

    The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. The Supplemental Treatment chosen will immobilize that portion of the retrieved LAW that is not sent to the WTP's LAW Vitrification facility into a solidified waste form. The solidified waste will then be disposed on the Hanford site in the Integrated Disposal Facility (IDF). In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as Cs-137, I-129, Tc-99, Cl, F, and SO4 that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap. The current waste disposal path for the WTP-SW is to recycle it to the supplemental LAW treatment to avoid a large steady state accumulation in the pretreatment-vitrification loop. Fluidized Bed Steam Reforming (FBSR) offers a moderate temperature (700-750 C) continuous method by which LAW and/or WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be as durable as LAW glass. Monolithing of the granular FBSR product is being investigated to prevent dispersion during transport or burial/storage but is not necessary for performance. A Benchscale Steam Reformer (BSR) was designed and constructed at the Savannah River National Laboratory (SRNL) to treat actual radioactive wastes to confirm the findings of the non-radioactive FBSR pilot scale tests and to qualify the waste form for applications at Hanford. Radioactive testing commenced in 2010 with a demonstration of Hanford's WTP-SW where Savannah River Site (SRS) High Level Waste (HLW) secondary waste from the Defense Waste Processing Facility (DWPF) was shimmed with a mixture of I-125/129 and Tc-99 to chemically resemble WTP-SW. Ninety six grams of radioactive product were made for testing. The second campaign commenced using SRS LAW chemically trimmed to look like Hanford's LAW. Six hundred grams of radioactive product were made for extensive testing and comparison to the non-radioactive pilot scale tests. The same mineral phases were found in the radioactive and non-radioactive testing.

  17. Identification and differentiation of individual beta emitters in waste mixtures by liquid scintillation spectrometry

    E-Print Network [OSTI]

    Siskel, Robin Lynn

    1988-01-01T23:59:59.000Z

    carbon-14, tritium, and iodine-125 liquid scintillation wastes, provided that the activity and isotopes present can be documented. This legislation has generated a significant interest in developing a quick, cost efficient method of identificatior... to reference data was the most practical method of unknown identification, and fully complies with regulatory requirements for relatively unquenched sample mixtures of two isotopes. Accurate isotopic identification and differentiation was found...

  18. Waste Management Effluent Treatment Facility: Phase I. CAC basic data

    SciTech Connect (OSTI)

    Gemar, D.W.; O'Leary, C.D.

    1984-03-23T23:59:59.000Z

    In order to expedite design and construction of the Waste Management Effluent Treatment Facility (WMETF), the project has been divided into two phases. Phase I consists of four storage basins and the associated transfer lines, diversion boxes, and control rooms. The design data pertaining to Phase I of the WMETF project are presented together with general background information and objectives for both phases. The project will provide means to store and decontaminate wastewater streams that are currently discharged to the seepage basins in F Area and H Area. This currently includes both routine process flows sent directly to the seepage basins and diversions of contaminated cooling water or storm water runoff that are stored in the retention basins before being pumped to the seepage basins.

  19. Phase I: the pipeline-gas demonstration plant. Demonstration plant engineering and design. Volume 18. Plant Section 2700 - Waste Water Treatment

    SciTech Connect (OSTI)

    none,

    1981-05-01T23:59:59.000Z

    Contract No. EF-77-C-01-2542 between Conoco Inc. and the US Department of Energy provides for the design, construction, and operation of a demonstration plant capable of processing bituminous caking coals into clean pipeline quality gas. The project is currently in the design phase (Phase I). This phase is scheduled to be completed in June 1981. One of the major efforts of Phase I is the process and project engineering design of the Demonstration Plant. The design has been completed and is being reported in 24 volumes. This is Volume 18 which reports the design of Plant Section 2700 - Waste Water Treatment. The objective of the Waste Water Treatment system is to collect and treat all plant liquid effluent streams. The system is designed to permit recycle and reuse of the treated waste water. Plant Section 2700 is composed of primary, secondary, and tertiary waste water treatment methods plus an evaporation system which eliminates liquid discharge from the plant. The Waste Water Treatment Section is designed to produce 130 pounds per hour of sludge that is buried in a landfill on the plant site. The evaporated water is condensed and provides a portion of the make-up water to Plant Section 2400 - Cooling Water.

  20. Application of Microbial Fuel Cell technology for a Waste Water Treatment Alternative

    E-Print Network [OSTI]

    Application of Microbial Fuel Cell technology for a Waste Water Treatment Alternative Eric A. Zielke February 15, 2006 #12;Application of Microbial Fuel Cell technology for a Waste Water Treatment Alternative Microbial fuel cells (MFCs) are devices that use bacteria to generate electricity from organic

  1. Characterization of oil and gas waste disposal practices and assessment of treatment costs. Final report

    SciTech Connect (OSTI)

    Bedient, P.B.

    1995-01-16T23:59:59.000Z

    This study examines wastes associated with the onshore exploration and production of crude oil and natural gas in the US. The objective of this study was to update and enhance the current state of knowledge with regard to oil and gas waste quantities, the potential environmental impact of these wastes, potential methods of treatment, and the costs associated with meeting various degrees of treatment. To meet this objective, the study consisted of three tasks: (1) the development of a production Environmental Database (PED) for the purpose of assessing current oil and gas waste volumes by state and for investigating the potential environmental impacts associated with current waste disposal practices on a local scale; (2) the evaluation of available and developing technologies for treating produced water waste streams and the identification of unit process configurations; and (3) the evaluation of the costs associated with various degrees of treatment achievable by different treatment configurations. The evaluation of feasible technologies for the treatment of produced water waste streams was handled in the context of comparing the level of treatment achievable with the associated cost of treatment. Treatment processes were evaluated for the removal of four categories of produced water contaminants: particulate material, volatile organic compounds, adsorbable organic compounds, and dissolved inorganic species. Results showed dissolved inorganic species to be the most costly to remove. The potential cost of treating all 18.3 billion barrels of produced water generated in a year amounts to some 15 billion dollars annually.

  2. Laboratory Scoping Tests Of Decontamination Of Hanford Waste Treatment Plant Low Activity Waste Off-Gas Condensate Simulant

    SciTech Connect (OSTI)

    Taylor-Pashow, Kathryn M.; Nash, Charles A.; Crawford, Charles L.; McCabe, Daniel J.; Wilmarth, William R.

    2014-01-21T23:59:59.000Z

    The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Off-Gas Condensate) from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable de-coupled operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of glass waste. This LAW Off-Gas Condensate stream contains components that are volatile at melter temperatures and are problematic for the glass waste form. Because this stream recycles within WTP, these components accumulate in the Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and diverting the stream reduces the halides in the recycled Condensate and is a key outcome of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, identifying a disposition path becomes vitally important. This task seeks to examine the potential treatment of this stream to remove radionuclides and subsequently disposition the decontaminated stream elsewhere, such as the Effluent Treatment Facility (ETF), for example. The treatment process envisioned is very similar to that used for the Actinide Removal Process (ARP) that has been operating for years at the Savannah River Site (SRS), and focuses on using mature radionuclide removal technologies that are also compatible with longterm tank storage and immobilization methods. For this new application, testing is needed to demonstrate acceptable treatment sorbents and precipitating agents and measure decontamination factors for additional radionuclides in this unique waste stream. The origin of this LAW Off-Gas Condensate stream will be the liquids from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW melter off-gas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover. The soluble components are expected to be mostly sodium and ammonium salts of nitrate, chloride, and fluoride. This stream has not been generated yet and will not be available until the WTP begins operation, but a simulant has been produced based on models, calculations, and comparison with pilot-scale tests. One of the radionuclides that is volatile and expected to be in high concentration in this LAW Off-Gas Condensate stream is Technetium-99 ({sup 99}Tc). Technetium will not be removed from the aqueous waste in the Hanford WTP, and will primarily end up immobilized in the LAW glass by repeated recycle of the off-gas condensate into the LAW melter. Other radionuclides that are also expected to be in appreciable concentration in the LAW Off-Gas Condensate are {sup 129}I, {sup 90}Sr, {sup 137}Cs, and {sup 241}Am. This report discusses results of preliminary radionuclide decontamination testing of the simulant. Testing examined use of Monosodium Titanate (MST) to remove {sup 90}Sr and actinides, inorganic reducing agents for {sup 99}Tc, and zeolites for {sup 137}Cs. Test results indicate that excellent removal of {sup 99}Tc was achieved using Sn(II)Cl{sub 2} as a reductant, coupled with sorption onto hydroxyapatite, even in the presence of air and at room temperature. This process was very effective at neutral pH, with a Decontamination Factor (DF) >577 in two hours. It was less effective at alkaline pH. Conversely, removal of the cesium was more effective at alka

  3. Evaluation of the transport and resuspension of a simulated nuclear waste slurry: Nuclear Waste Treatment Program

    SciTech Connect (OSTI)

    Carleson, T.E.; Drown, D.C.; Hart, R.E.; Peterson, M.E.

    1987-09-01T23:59:59.000Z

    The Department of Chemical Engineering at the University of Idaho conducted research on the transport and resuspension of a simulated high-level nuclear waste slurry. In the United States, the reference process for treating both defense and civilian HLLW is vitrification using the liquid-fed ceramic melter process. The non-Newtonian behavior of the slurry complicates the evaluation of the transport and resuspension characteristics of the slurry. The resuspension of a simulated (nonradioactive) melter feed slurry was evaluated using a slurry designated as WV-205. The simulated slurry was developed for the West Valley Demonstration Project and was used during a pilot-scale ceramic melter (PSCM) experiment conducted at PNL in July 1985 (PSCM-21). This study involved determining the transport characteristics of a fully suspended slurry and the resuspension characteristics of settled solids in a pilot-scale pipe loop. The goal was to predict the transport and resuspension of a full-scale system based on rheological data for a specific slurry. The rheological behavior of the slurry was evaluated using a concentric cylinder rotational viscometer, a capillary tube viscometer, and the pilot-scale pipe loop. The results obtained from the three approaches were compared. 40 refs., 74 figs., 15 tabs.

  4. RADIOACTIVE DEMONSTRATION OF FINAL MINERALIZED WASTE FORMS FOR HANFORD WASTE TREATMENT PLANT SECONDARY WASTE BY FLUIDIZED BED STEAM REFORMING USING THE BENCH SCALE REFORMER PLATFORM

    SciTech Connect (OSTI)

    Crawford, C.; Burket, P.; Cozzi, A.; Daniel, W.; Jantzen, C.; Missimer, D.

    2012-02-02T23:59:59.000Z

    The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as {sup 137}Cs, {sup 129}I, {sup 99}Tc, Cl, F, and SO{sub 4} that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap (that could minimize volatilization). The current waste disposal path for the WTP-SW is to process it through the Effluent Treatment Facility (ETF). Fluidized Bed Steam Reforming (FBSR) is being considered for immobilization of the ETF concentrate that would be generated by processing the WTP-SW. The focus of this current report is the WTP-SW. FBSR offers a moderate temperature (700-750 C) continuous method by which WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be as durable as LAW glass. Monolithing of the granular FBSR product is being investigated to prevent dispersion during transport or burial/storage, but is not necessary for performance. A Benchscale Steam Reformer (BSR) was designed and constructed at the SRNL to treat actual radioactive wastes to confirm the findings of the non-radioactive FBSR pilot scale tests and to qualify the waste form for applications at Hanford. BSR testing with WTP SW waste surrogates and associated analytical analyses and tests of granular products (GP) and monoliths began in the Fall of 2009, and then was continued from the Fall of 2010 through the Spring of 2011. Radioactive testing commenced in 2010 with a demonstration of Hanford's WTP-SW where Savannah River Site (SRS) High Level Waste (HLW) secondary waste from the Defense Waste Processing Facility (DWPF) was shimmed with a mixture of {sup 125/129}I and {sup 99}Tc to chemically resemble WTP-SW. Prior to these radioactive feed tests, non-radioactive simulants were also processed. Ninety six grams of radioactive granular product were made for testing and comparison to the non-radioactive pilot scale tests. The same mineral phases were found in the radioactive and non-radioactive testing.

  5. The mutagenic potential of soil and runoff water from land treatment of three hazardous industrial wastes

    E-Print Network [OSTI]

    Davol, Phebe

    1987-01-01T23:59:59.000Z

    of agricultural chemicals and the performance of hazardous waste land treatment facilities. This study used a bioassay directed chemical analysis protocol to monitor the environmental fate of mutagenic constituents from a simulated land treatment demonstration...THE MUTAGENIC POTENTIAL OF SOIL AND RUNOFF WATER FROM LAND TREATMENT OF THREE HAZARDOUS INDUSTRIAL WASTES A Thesis by PHEBE DAYOL Submitted to the Graduate College of Te xa s ASM Un i ver s i ty in partial fulfillment of the requirement...

  6. Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario Hydro`s Bruce Nuclear Generating Station `A`

    SciTech Connect (OSTI)

    Day, J.E.; Baker, R.L.

    1995-05-01T23:59:59.000Z

    Ontario Hydro at the Bruce Nuclear Generating Station `A` has undertaken a program to render the station`s liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants to satisfy regulatory requirements for emissions. The system will remove radionuclide and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology.

  7. Documentation on currently operating low-level radioactive waste treatment systems: National Low-Level Waste Management Program

    SciTech Connect (OSTI)

    Not Available

    1987-11-01T23:59:59.000Z

    In May 1985, the US Department of Energy issued a Program Research and Development Announcement requesting documentation on currently operating low-level radioactive waste treatment systems. Six grants were awarded to support that documentation. Final reports for the following grants and grantees are compiled in this document: Shredder/Compactor Report by Impell Corp., Volume Reduction and Solidification System for Low-Level Radwaste Treatment by Waste Chem Corp., Low-Level Radioactive Waste Treatment Systems in Northern Europe by Pacific Nuclear Services/Nuclear Packaging Inc., The University of Missouri Research Reactor Facility Can Melter System by the University of Missouri, Drying of Ion-Exchange Resin and Filter Media by Nuclear Packaging Inc., and Operational Experience with Selective Ion-Exchange Media in Sluiceable Pressurized Demineralizers at Nuclear Power Plants by Analytical Resources Inc. 65 refs., 4 figs., 7 tabs.

  8. Sampling and Analysis Plan Waste Treatment Plant Seismic Boreholes Project.

    SciTech Connect (OSTI)

    Brouns, Thomas M.

    2007-07-15T23:59:59.000Z

    This sampling and analysis plan (SAP) describes planned data collection activities for four entry boreholes through the sediment overlying the Saddle Mountains Basalt, up to three new deep rotary boreholes through the Saddle Mountains Basalt and sedimentary interbeds, and one corehole through the Saddle Mountains Basalt and sedimentary interbeds at the Waste Treatment Plant (WTP) site. The SAP will be used in concert with the quality assurance plan for the project to guide the procedure development and data collection activities needed to support borehole drilling, geophysical measurements, and sampling. This SAP identifies the American Society of Testing Materials standards, Hanford Site procedures, and other guidance to be followed for data collection activities. Revision 3 incorporates all interim change notices (ICN) that were issued to Revision 2 prior to completion of sampling and analysis activities for the WTP Seismic Boreholes Project. This revision also incorporates changes to the exact number of samples submitted for dynamic testing as directed by the U.S. Army Corps of Engineers. Revision 3 represents the final version of the SAP.

  9. Compositions and methods useful for ionic liquid treatment of biomass

    DOE Patents [OSTI]

    Dibble, Dean C.; Cheng, Aurelia; George, Anthe

    2014-07-29T23:59:59.000Z

    The present invention provides for novel compositions and methods for recycling or recovering ionic liquid used in IL pretreated cellulose and/or lignocellulosic biomass (LBM).

  10. Processing liquid radioactive waste by centrifuge and indrum dehydration facility at NPP Philippsburg

    SciTech Connect (OSTI)

    Grundke, E.; Blaser, W. [NPP Philippsburg (Germany)

    1993-12-31T23:59:59.000Z

    Until 1989 the evaporator and filter concentrates have been treated by concreting. The centrifuge facility is used for the liquid waste from laundry, showers and also for processing filter concentrates and evaporator feedwater. The hot high pressure compacting of filter concentrates gives a volume reduction by a factor of 6. The evaporator concentrate is drained in a 200 l drum and this drum is heated by an external heating device. The indrum-dehydration facility reduces the treated volume by a factor of 12 compared with the former cementation.

  11. Use of tangential filtration unit for processing liquid waste from nuclear laundries

    SciTech Connect (OSTI)

    Augustin, X.; Buzonniere, A. de [Technicatome, Gif-sur-Yvette (France); Barnier, H. [CEA Cadarache, St. Paul-lez-Durance (France)

    1993-12-31T23:59:59.000Z

    Nuclear facilities produce large quantities of weakly contaminated effluents charged with insoluble and soluble products. In collaboration with CEA, TECHNICATOME has developed an ultrafiltration process for liquid waste from nuclear facilities associated with prior insolubilization of radiochemical activity. This process, seeded ultrafiltration, is based on the use of a decloggable mineral filter media and combines very high separation efficiency with long membrane life. The efficiency of the tangential filtration unit which has been processing effluents from the Cadarache Nuclear Research Center (CEA-France) nuclear facility since mid-1988, has been confirmed on several sites.

  12. Modeling Hydrogen Generation Rates in the Hanford Waste Treatment and Immobilization Plant

    SciTech Connect (OSTI)

    Camaioni, Donald M.; Bryan, Samuel A.; Hallen, Richard T.; Sherwood, David J.; Stock, Leon M.

    2004-03-29T23:59:59.000Z

    This presentation describes a project in which Hanford Site and Environmental Management Science Program investigators addressed issues concerning hydrogen generation rates in the Hanford waste treatment and immobilization plant. The hydrogen generation rates of radioactive wastes must be estimated to provide for safe operations. While an existing model satisfactorily predicts rates for quiescent wastes in Hanford underground storage tanks, pretreatment operations will alter the conditions and chemical composition of these wastes. Review of the treatment process flowsheet identified specific issues requiring study to ascertain whether the model would provide conservative values for waste streams in the plant. These include effects of adding hydroxide ion, alpha radiolysis, saturation with air (oxygen) from pulse-jet mixing, treatment with potassium permanganate, organic compounds from degraded ion exchange resins and addition of glass-former chemicals. The effects were systematically investigated through literature review, technical analyses and experimental work.

  13. Technology Evaluations Related to Mercury, Technetium, and Chloride in Treatment of Wastes at the Idaho Nuclear Technology and Engineering Center of the Idaho National Engineering and Environmental Laboratory

    SciTech Connect (OSTI)

    C. M. Barnes; D. D. Taylor; S. C. Ashworth; J. B. Bosley; D. R. Haefner

    1999-10-01T23:59:59.000Z

    The Idaho High-Level Waste and Facility Disposition Environmental Impact Statement defines alternative for treating and disposing of wastes stored at the Idaho Nuclear Technology and Engineering Center. Development is required for several technologies under consideration for treatment of these wastes. This report contains evaluations of whether specific treatment is needed and if so, by what methods, to remove mercury, technetium, and chlorides in proposed Environmental Impact Statement treatment processes. The evaluations of mercury include a review of regulatory requirements that would apply to mercury wastes in separations processes, an evaluation of the sensitivity of mercury flowrates and concentrations to changes in separations processing schemes and conditions, test results from laboratory-scale experiments of precipitation of mercury by sulfide precipitation agents from the TRUEX carbonate wash effluent, and evaluations of methods to remove mercury from New Waste Calcining Facility liquid and gaseous streams. The evaluation of technetium relates to the need for technetium removal and alternative methods to remove technetium from streams in separations processes. The need for removal of chlorides from New Waste Calcining Facility scrub solution is also evaluated.

  14. Treatment of EBR-I NaK mixed waste at Argonne National Laboratory and subsequent land disposal at the Idaho National Engineering and Environmental Laboratory.

    SciTech Connect (OSTI)

    Herrmann, S. D.; Buzzell, J. A.; Holzemer, M. J.

    1998-02-03T23:59:59.000Z

    Sodium/potassium (NaK) liquid metal coolant, contaminated with fission products from the core meltdown of Experimental Breeder Reactor I (EBR-I) and classified as a mixed waste, has been deactivated and converted to a contact-handled, low-level waste at Argonne's Sodium Component Maintenance Shop and land disposed at the Radioactive Waste Management Complex. Treatment of the EBR-I NaK involved converting the sodium and potassium to its respective hydroxide via reaction with air and water, followed by conversion to its respective carbonate via reaction with carbon dioxide. The resultant aqueous carbonate solution was solidified in 55-gallon drums. Challenges in the NaK treatment involved processing a mixed waste which was incompletely characterized and difficult to handle. The NaK was highly radioactive, i.e. up to 4.5 R/hr on contact with the mixed waste drums. In addition, the potential existed for plutonium and toxic characteristic metals to be present in the NaK, resultant from the location of the partial core meltdown of EBR-I in 1955. Moreover, the NaK was susceptible to degradation after more than 40 years of storage in unmonitored conditions. Such degradation raised the possibility of energetic exothermic reactions between the liquid NaK and its crust, which could have consisted of potassium superoxide as well as hydrated sodium/potassium hydroxides.

  15. Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory. Part 1, Waste streams and treatment technologies

    SciTech Connect (OSTI)

    Neupauer, R.M.; Thurmond, S.M.

    1992-09-01T23:59:59.000Z

    This report describes health and safety concerns associated with the Mixed and Low-level Waste Treatment Facility at the Idaho National Engineering Laboratory. Various hazards are described such as fire, electrical, explosions, reactivity, temperature, and radiation hazards, as well as the potential for accidental spills, exposure to toxic materials, and other general safety concerns.

  16. EIS-0133: Decontamination and Waste Treatment Facility for the Lawrence Livermore National Laboratory Livermore, California

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy’s San Francisco Operations Office developed this statement to analyze the potential environmental and socioeconomic impacts of alternatives for constructing and operating a Decontamination and Waste Treatment Facility for nonradioactive (hazardous and nonhazardous) mixed and radioactive wastes at Lawrence Livermore National Laboratory.

  17. Development And Initial Testing Of Off-Gas Recycle Liquid From The WTP Low Activity Waste Vitrification Process - 14333

    SciTech Connect (OSTI)

    McCabe, Daniel J.; Wilmarth, William R.; Nash, Charles A.; Taylor-Pashow, Kathryn M.; Adamson, Duane J.; Crawford, Charles L.; Morse, Megan M.

    2014-01-07T23:59:59.000Z

    The Waste Treatment and Immobilization Plant (WTP) process flow was designed to pre-treat feed from the Hanford tank farms, separate it into a High Level Waste (HLW) and Low Activity Waste (LAW) fraction and vitrify each fraction in separate facilities. Vitrification of the waste generates an aqueous condensate stream from the off-gas processes. This stream originates from two off-gas treatment unit operations, the Submerged Bed Scrubber (SBS) and the Wet Electrospray Precipitator (WESP). Currently, the baseline plan for disposition of the stream from the LAW melter is to recycle it to the Pretreatment facility where it gets evaporated and processed into the LAW melter again. If the Pretreatment facility is not available, the baseline disposition pathway is not viable. Additionally, some components in the stream are volatile at melter temperatures, thereby accumulating to high concentrations in the scrubbed stream. It would be highly beneficial to divert this stream to an alternate disposition path to alleviate the close-coupled operation of the LAW vitrification and Pretreatment facilities, and to improve long-term throughput and efficiency of the WTP system. In order to determine an alternate disposition path for the LAW SBS/WESP Recycle stream, a range of options are being studied. A simulant of the LAW Off-Gas Condensate was developed, based on the projected composition of this stream, and comparison with pilot-scale testing. The primary radionuclide that vaporizes and accumulates in the stream is Tc-99, but small amounts of several other radionuclides are also projected to be present in this stream. The processes being investigated for managing this stream includes evaporation and radionuclide removal via precipitation and adsorption. During evaporation, it is of interest to investigate the formation of insoluble solids to avoid scaling and plugging of equipment. Key parameters for radionuclide removal include identifying effective precipitation or ion adsorption chemicals, solid-liquid separation methods, and achievable decontamination factors. Results of the radionuclide removal testing indicate that the radionuclides, including Tc-99, can be removed with inorganic sorbents and precipitating agents. Evaporation test results indicate that the simulant can be evaporated to fairly high concentration prior to formation of appreciable solids, but corrosion has not yet been examined.

  18. Site-Specific Seismic Site Response Model for the Waste Treatment Plant, Hanford, Washington

    SciTech Connect (OSTI)

    Rohay, Alan C.; Reidel, Steve P.

    2005-02-24T23:59:59.000Z

    This interim report documents the collection of site-specific geologic and geophysical data characterizing the Waste Treatment Plant site and the modeling of the site-specific structure response to earthquake ground motions.

  19. EA-1189: Non-thermal Treatment of Hanford Site Low-level Mixed Waste, Richland, Washington

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts for the proposal to demonstrate the feasibility of commercial treatment of contact-handled low-level mixed waste to meet existing Federal and State...

  20. EA-1292: On-site Treatment of Low Level Mixed Waste, Golden, Colorado

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts for the proposal to evaluate the proposed treatment of low level mixed waste at the U.S. Department of Energy's Rocky Flats Environmental Technology Site.

  1. Department of Energy treatment capabilities for greater-than-Class C low-level radioactive waste

    SciTech Connect (OSTI)

    Morrell, D.K.; Fischer, D.K.

    1995-01-01T23:59:59.000Z

    This report provides brief profiles for 26 low-level and high-level waste treatment capabilities available at the Idaho National Engineering Laboratory (INEL), Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Pacific Northwest Laboratory (PNL), Rocky Flats Plant (RFP), Savannah River Site (SRS), and West Valley Demonstration Plant (WVDP). Six of the treatments have potential use for greater-than-Class C low-level waste (GTCC LLW). They include: (a) the glass ceramic process and (b) the Waste Experimental Reduction Facility incinerator at INEL; (c) the Super Compaction and Repackaging Facility and (d) microwave melting solidification at RFP; (e) the vitrification plant at SRS; and (f) the vitrification plant at WVDP. No individual treatment has the capability to treat all GTCC LLW streams. It is recommended that complete physical and chemical characterizations be performed for each GTCC waste stream, to permit using multiple treatments for GTCC LLW.

  2. Nitric-phosphoric acid treatment of TRU wastes

    SciTech Connect (OSTI)

    Smith, J.R.; Pierce, R.A.; Sturcken, E.F.

    1993-09-30T23:59:59.000Z

    A general process is being developed for the treatment of solid TRU and hazardous organic waste. Experimental data indicates that 100 lb/hr of aliphatic organic (plastics) and 1,000 lb/hr of non-aliphatic organic compounds can be quantitatively oxidized in a 1,000 gallon reaction vessel. The process uses dilute nitric acid in a concentrated phosphoric acid media as the main oxidant for the organic compounds. Phosphoric acid allows oxidation at temperatures up to 200{degrees}C and is relatively non-corrosive on 304-L stainless steel, especially at room temperature. Many organic materials have been completely oxidized to CO{sub 2}, CO, and inorganic acids in a 0.1M HNO{sub 3}/14.8M H{sub 3}PO{sub 4} solution. Addition of 0.001M Pd{sup 2+} reduces the CO to near 1% of the released carbon gases. To accomplish complete oxidation the solution temperature must be maintained above 130--150{degrees}C. Organic materials quantitatively destroyed include neoprene, cellulose, EDTA, TBP, tartaric acid, and nitromethane. The oxidation is usually complete in a few hours for soluble organic materials. The oxidation rate for non-aliphatic organic solids is moderately fast and surface area dependent. Polyethylene is quantitatively oxidized in 1.0M HNO{sub 3}/13.8M H{sub 3}PO{sub 4} solution while contained in pressure vessels heated with microwave energy. This is probably due to the high concentrations of NO{sub 2}{center_dot} obtained in the reaction environment.

  3. Mechanical-biological waste treatment and the associated occupational hygiene in Finland

    SciTech Connect (OSTI)

    Tolvanen, Outi K. [University of Jyvaeskylae, Department of Environmental and Biological Sciences, P.O. Box 35, 40014 University of Jyvaeskylae (Finland)]. E-mail: outolvan@bytl.jyu.fi; Haenninen, Kari I. [University of Jyvaeskylae, Department of Environmental and Biological Sciences, P.O. Box 35, 40014 University of Jyvaeskylae (Finland)

    2006-07-01T23:59:59.000Z

    A special feature of waste management in Finland has been the emphasis on the source separation of kitchen biowaste (catering waste); more than two-thirds of the Finnish population participates in this separation. Source-separated biowaste is usually treated by composting. The biowaste of about 5% of the population is handled by mechanical-biological treatment. A waste treatment plant at Mustasaari is the only plant in Finland using digestion for kitchen biowaste. For the protection of their employees, the plant owners commissioned a study on environmental factors and occupational hygiene in the plant area. During 1998-2000 the concentrations of dust, microbes and endotoxins and noise levels were investigated to identify possible problems at the plant. Three different work areas were investigated: the pre-processing and crushing hall, the bioreactor hall and the drying hall. Employees were asked about work-related health problems. Some problems with occupational hygiene were identified: concentrations of microbes and endotoxins may increase to levels harmful to health during waste crushing and in the bioreactor hall. Because employees complained of symptoms such as dry cough and rash or itching appearing once or twice a month, it is advisable to use respirator masks (class P3) during dusty working phases. The noise level in the drying hall exceeded the Finnish threshold value of 85 dBA. Qualitatively harmful factors for the health of employees are similar in all closed waste treatment plants in Finland. Quantitatively, however, the situation at the Mustasaari treatment plant is better than at some Finnish dry waste treatment plants. Therefore is reasonable to conclude that mechanical sorting, which produces a dry waste fraction for combustion and a biowaste fraction for anaerobic treatment, is in terms of occupational hygiene better for employees than combined aerobic treatment and dry waste treatment.

  4. ASPEN computer simulations of the mixed waste treatment project baseline flowsheet

    SciTech Connect (OSTI)

    Dietsche, L.J.; Upadhye, R.S.; Camp, D.W.; Pendergrass, J.A.; Borduin, L.C.; Thompson, T.K.

    1994-07-05T23:59:59.000Z

    The treatment and disposal of mixed waste (i.e., waste containing both hazardous and radioactive components) is a challenging waste- management problem of particular concern to Department of Energy (DOE) sites throughout the United States. Traditional technologies used for destroying hazardous wastes must be re- evaluated for their ability to handle mixed wastes, and, in some cases, new technologies must be developed. The Mixed Waste Treatment Project (MWTP), a collaborative effort between Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory, and Pacific Northwest Laboratory (PNL), was established by the DOE`s Waste Operations Program (EM-30) to develop and analyze alternative mixed waste treatment approaches. One of the MWTP`s initiatives, and the objective of this study, was to develop flowsheets for prototype, integrated, mixed-waste treatment facilities that can serve as models for sites developing their own treatment strategies. Evaluation of these flowsheets is being facilitated through the use of computer modeling. The objectives of the flowsheet simulations are to compare process effectiveness and costs of alternative flowsheets and to determine if commercial process-simulation software could be used on the large, complex process of an integrated mixed waste processing facility. Flowsheet modeling is needed to evaluate many aspects of proposed flowsheet designs. A major advantage of modeling the complete flowsheet is the ability to define the internal recycle streams, thereby making it possible to evaluate the impact of one operation on the whole plant. Many effects that can be seen only in this way. Modeling also can be used to evaluate sensitivity and range of operating conditions, radioactive criticality, and relative costs of different flowsheet designs. Further, the modeled flowsheets must be easily modified so that one can examine how alternative technologies and varying feed streams affect the overall integrated process.

  5. Biological treatment of concentrated hazardous, toxic, andradionuclide mixed wastes without dilution

    SciTech Connect (OSTI)

    Stringfellow, William T.; Komada, Tatsuyuki; Chang, Li-Yang

    2004-06-15T23:59:59.000Z

    Approximately 10 percent of all radioactive wastes produced in the U. S. are mixed with hazardous or toxic chemicals and therefore can not be placed in secure land disposal facilities. Mixed wastes containing hazardous organic chemicals are often incinerated, but volatile radioactive elements are released directly into the biosphere. Some mixed wastes do not currently have any identified disposal option and are stored locally awaiting new developments. Biological treatment has been proposed as a potentially safer alternative to incineration for the treatment of hazardous organic mixed wastes, since biological treatment would not release volatile radioisotopes and the residual low-level radioactive waste would no longer be restricted from land disposal. Prior studies have shown that toxicity associated with acetonitrile is a significant limiting factor for the application of biotreatment to mixed wastes and excessive dilution was required to avoid inhibition of biological treatment. In this study, we demonstrate that a novel reactor configuration, where the concentrated toxic waste is drip-fed into a complete-mix bioreactor containing a pre-concentrated active microbial population, can be used to treat a surrogate acetonitrile mixed waste stream without excessive dilution. Using a drip-feed bioreactor, we were able to treat a 90,000 mg/L acetonitrile solution to less than 0.1 mg/L final concentration using a dilution factor of only 3.4. It was determined that the acetonitrile degradation reaction was inhibited at a pH above 7.2 and that the reactor could be modeled using conventional kinetic and mass balance approaches. Using a drip-feed reactor configuration addresses a major limiting factor (toxic inhibition) for the biological treatment of toxic, hazardous, or radioactive mixed wastes and suggests that drip-feed bioreactors could be used to treat other concentrated toxic waste streams, such as chemical warfare materiel.

  6. Bioaugmentation for the treatment of oilfield drilling waste

    SciTech Connect (OSTI)

    Barber, T.P. [BioGEE International, Inc., Houston, TX (United States)

    1997-06-01T23:59:59.000Z

    Disposal of oilfield drilling pit waste is a problem for the petroleum industry. In the past, drilling pits were covered with dirt of the waste was excavated and hauled to a landfill. Bioremediation can clean-up the waste and save the oilfield drillers money and headaches. Bioremediation is the technique of using microbes capable of metabolizing hydrocarbons into environmentally safe water and carbon dioxide. Drilling companies can utilize bioremediation to treat the petroleum wastes in-situ rather than transport the waste. BioGEE has developed a procedure to use in-situ bioremediation on drilling wastes. After environmental conditions are adjusted, hydrocarbon degrading microbes and nutrients are applied. Drilling wastes consist primarily of hydrocarbons. An average well has a total petroleum hydrocarbon (TPH) level of 44,880 PPM. Using BioGEE`s bioremediation technology, TPH levels have successfully been lowered to below the maximum allowable level of 10,000 PPM to 6,486 PPM of TPH in 47 days.

  7. MWIP: Surrogate formulations for thermal treatment of low-level mixed waste. Part 4, Wastewater treatment sludges

    SciTech Connect (OSTI)

    Bostick, W.D.; Hoffmann, D.P.; Stevenson, R.J.; Richmond, A.A. [Oak Ridge National Lab., TN (United States); Bickford, D.F. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1994-01-01T23:59:59.000Z

    The category of sludges, filter cakes, and other waste processing residuals represent the largest volume of low-level mixed (hazardous and radioactive) wastes within the US Department of Energy (DOE) complex. Treatment of these wastes to minimize the mobility of contaminants, and to eliminate the presence of free water, is required under the Federal Facility Compliance Act agreements between DOE and the Environmental Protection Agency. In the text, we summarize the currently available data for several of the high priority mixed-waste sludge inventories within DOE. Los Alamos National Laboratory TA-50 Sludge and Rocky Flats Plant By-Pass Sludge are transuranic (TRU)-contaminated sludges that were isolated with the use of silica-based filter aids. The Oak Ridge Y-12 Plant West End Treatment Facility Sludge is predominantly calcium carbonate and biomass. The Oak Ridge K-25 Site Pond Waste is a large-volume waste stream, containing clay, silt, and other debris in addition to precipitated metal hydroxides. We formulate ``simulants`` for the waste streams described above, using cerium oxide as a surrogate for the uranium or plutonium present in the authentic material. Use of nonradiological surrogates greatly simplifies material handling requirements for initial treatability studies. The use of synthetic mixtures for initial treatability testing will facilitate compositional variation for use in conjunction with statistical design experiments; this approach may help to identify any ``operating window`` limitations. The initial treatability testing demonstrations utilizing these ``simulants`` will be based upon vitrification, although the materials are also amenable to testing grout-based and other stabilization procedures. After the feasibility of treatment and the initial evaluation of treatment performance has been demonstrated, performance must be verified using authentic samples of the candidate waste stream.

  8. Adsorption of Ruthenium, Rhodium and Palladium from Simulated High-Level Liquid Waste by Highly Functional Xerogel - 13286

    SciTech Connect (OSTI)

    Onishi, Takashi [Fukushima Fuels and Materials Department O-arai Research and Development Center Japan Atomic Energy Agency, Narita-cho 4002, O-arai-machi, Ibaraki, 311-1393 (Japan)] [Fukushima Fuels and Materials Department O-arai Research and Development Center Japan Atomic Energy Agency, Narita-cho 4002, O-arai-machi, Ibaraki, 311-1393 (Japan); Koyama, Shin-ichi [Fukushima Fuels and Materials Department O-arai Research and Development Center Japan Atomic Energy Agency, Narita-cho 4002, O-arai-machi, Ibaraki, 311-1393 (Japan)] [Fukushima Fuels and Materials Department O-arai Research and Development Center Japan Atomic Energy Agency, Narita-cho 4002, O-arai-machi, Ibaraki, 311-1393 (Japan); Mimura, Hitoshi [Dept. of Quantum Science and Energy Engineering, Graduate School of Engineering, Tohoku University Aramaki-Aza-Aoba 6-6-01-2,Aoba-ku, Sendai-shi, Miyagi-ken, 980-8579 (Japan)] [Dept. of Quantum Science and Energy Engineering, Graduate School of Engineering, Tohoku University Aramaki-Aza-Aoba 6-6-01-2,Aoba-ku, Sendai-shi, Miyagi-ken, 980-8579 (Japan)

    2013-07-01T23:59:59.000Z

    Fission products are generated by fission reactions in nuclear fuel. Platinum group (Pt-G) elements, such as palladium (Pd), rhodium (Rh) and ruthenium (Ru), are also produced. Generally, Pt-G elements play important roles in chemical and electrical industries. Highly functional xerogels have been developed for recovery of these useful Pt-G elements from high - level radioactive liquid waste (HLLW). An adsorption experiment from simulated HLLW was done by the column method to study the selective adsorption of Pt-G elements, and it was found that not only Pd, Rh and Ru, but also nickel, zirconium and tellurium were adsorbed. All other elements were not adsorbed. Adsorbed Pd was recovered by washing the xerogel-packed column with thiourea solution and thiourea - nitric acid mixed solution in an elution experiment. Thiourea can be a poison for automotive exhaust emission system catalysts, so it is necessary to consider its removal. Thermal decomposition and an acid digestion treatment were conducted to remove sulfur in the recovered Pd fraction. The relative content of sulfur to Pd was decreased from 858 to 0.02 after the treatment. These results will contribute to design of the Pt-G element separation system. (authors)

  9. EXPLORING ENGINEERING CONTROL THROUGH PROCESS MANIPULATION OF RADIOACTIVE LIQUID WASTE TANK CHEMICAL CLEANING

    SciTech Connect (OSTI)

    Brown, A.

    2014-04-27T23:59:59.000Z

    One method of remediating legacy liquid radioactive waste produced during the cold war, is aggressive in-tank chemical cleaning. Chemical cleaning has successfully reduced the curie content of residual waste heels in large underground storage tanks; however this process generates significant chemical hazards. Mercury is often the bounding hazard due to its extensive use in the separations process that produced the waste. This paper explores how variations in controllable process factors, tank level and temperature, may be manipulated to reduce the hazard potential related to mercury vapor generation. When compared using a multivariate regression analysis, findings indicated that there was a significant relationship between both tank level (p value of 1.65x10{sup -23}) and temperature (p value of 6.39x10{sup -6}) to the mercury vapor concentration in the tank ventilation system. Tank temperature showed the most promise as a controllable parameter for future tank cleaning endeavors. Despite statistically significant relationships, there may not be confidence in the ability to control accident scenarios to below mercury’s IDLH or PAC-III levels for future cleaning initiatives.

  10. Sampling and analysis of radioactive liquid wastes and sludges in the Melton Valley and evaporator facility storage tanks at ORNL

    SciTech Connect (OSTI)

    Sears, M.B.; Botts, J.L.; Ceo, R.N.; Ferrada, J.J.; Griest, W.H.; Keller, J.M.; Schenley, R.L.

    1990-09-01T23:59:59.000Z

    The sampling and analysis of the radioactive liquid wastes and sludges in the Melton Valley Storage Tanks (MVSTs), as well as two of the evaporator service facility storage tanks at ORNL, are described. Aqueous samples of the supernatant liquid and composite samples of the sludges were analyzed for major constituents, radionuclides, total organic carbon, and metals listed as hazardous under the Resource Conservation and Recovery Act (RCRA). Liquid samples from five tanks and sludge samples from three tanks were analyzed for organic compounds on the Environmental Protection Agency (EPA) Target Compound List. Estimates were made of the inventory of liquid and sludge phases in the tanks. Descriptions of the sampling and analytical activities and tabulations of the results are included. The report provides data in support of the design of the proposed Waste Handling and Packaging Plant, the Liquid Low-Level Waste Solidification Project, and research and development activities (R D) activities in developing waste management alternatives. 7 refs., 8 figs., 16 tabs.

  11. Leaching characteristics of the metal waste form from the electrometallurgical treatment process: Product consistency testing

    SciTech Connect (OSTI)

    Johnson, S. G.; Keiser, D. D.; Frank, S. M.; DiSanto, T.; Noy, M.

    1999-11-11T23:59:59.000Z

    Argonne National Laboratory is developing an electrometallurgical treatment for spent fuel from the experimental breeder reactor II. A product of this treatment process is a metal waste form that incorporates the stainless steel cladding hulls, zirconium from the fuel and the fission products that are noble to the process, i.e., Tc, Ru, Nb, Pd, Rh, Ag. The nominal composition of this waste form is stainless steel/15 wt% zirconium/1--4 wt% noble metal fission products/1--2 wt % U. Leaching results are presented from several tests and sample types: (1) 2 week monolithic immersion tests on actual metal waste forms produced from irradiated cladding hulls, (2) long term (>2 years) pulsed flow tests on samples containing technetium and uranium and (3) crushed sample immersion tests on cold simulated metal waste form samples. The test results will be compared and their relevance for waste form product consistency testing discussed.

  12. US Department of Energy mixed waste characterization, treatment, and disposal focus area technical baseline development process

    SciTech Connect (OSTI)

    Roach, J.A.; Gombert, D. [Lockheed Martin Idaho Technologies, Idaho Falls, ID (United States)

    1996-12-31T23:59:59.000Z

    The US Department of Energy (DOE) created the Mixed Waste Characterization, Treatment, and Disposal Focus Area (MWFA) to develop and facilitate implementation of technologies required to meet its commitments for treatment of mixed wastes under the Federal Facility Compliance Act (FFCA), and in accordance with the Land Disposal Restrictions (LDR) of the Resource Conservation and Recovery Act (RCRA). Mixed wastes include both mixed low-level waste (MLLW) and mixed transuranic (MTRU) waste. The goal of the MWFA is to develop mixed waste treatment systems to the point of implementation by the Environmental Management (EM) customer. To accomplish this goal, the MWFA is utilizing a three step process. First, the treatment system technology deficiencies were identified and categorized. Second, these identified needs were prioritized. This resulted in a list of technical deficiencies that will be used to develop a technical baseline. The third step, the Technical Baseline Development Process, is currently ongoing. When finalized, the technical baseline will integrate the requirements associated with the identified needs into the planned and ongoing environmental research and technology development activities supported by the MWFA. Completion of this three-step process will result in a comprehensive technology development program that addresses customer identified and prioritized needs. The MWFA technical baseline will be a cost-effective, technically-defensible tool for addressing and resolving DOE`s mixed waste problems.

  13. Treatment plan for aqueous/organic/decontamination wastes under the Oak Ridge Reservation FFCA Development, Demonstration, Testing, and Evaluation Program

    SciTech Connect (OSTI)

    Backus, P.M.; Benson, C.E.; Gilbert, V.P.

    1994-08-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) Oak Ridge Operations Office and the U.S. Environmental Protection Agency (EPA)-Region IV have entered into a Federal Facility Compliance Agreement (FFCA) which seeks to facilitate the treatment of low-level mixed wastes currently stored at the Oak Ridge Reservation (ORR) in violation of the Resource, Conservation and Recovery Act Land Disposal Restrictions. The FFCA establishes schedules for DOE to identify treatment for wastes, referred to as Appendix B wastes, that current have no identified or existing capacity for treatment. A development, demonstration, testing, and evaluation (DDT&E) program was established to provide the support necessary to identify treatment methods for mixed was meeting the Appendix B criteria. The Program has assembled project teams to address treatment development needs for major categories of the Appendix B wastes based on the waste characteristics and possible treatment technologies. The Aqueous, Organic, and Decontamination (A/O/D) project team was established to identify pretreatment options for aqueous and organic wastes which will render the waste acceptable for treatment in existing waste treatment facilities and to identify the processes to decontaminate heterogeneous debris waste. In addition, the project must also address the treatment of secondary waste generated by other DDT&E projects. This report details the activities to be performed under the A/O/D Project in support of the identification, selection, and evaluation of treatment processes. The goals of this plan are (1) to determine the major aqueous and organic waste streams requiring treatment, (2) to determine the treatment steps necessary to make the aqueous and organic waste acceptable for treatment in existing treatment facilities on the ORR or off-site, and (3) to determine the processes necessary to decontaminate heterogeneous wastes that are considered debris.

  14. Treatment technologies for hazardous ashes generated from possible incineration of navy waste. Technical note

    SciTech Connect (OSTI)

    Torres, T.

    1990-10-01T23:59:59.000Z

    The Navy recognizes that thermal treatment of Navy hazardous wastes (HW) should, under the terms of the Resource Conservation and Recovery Act of 1976, be avoided. Combustion waste disposal may nonetheless become unavoidable in certain cases, even after all possible process enhancements that avoid HW production are implemented. Even then, some toxic constituents that may be present in the waste will not be destroyed by incineration and will persist in the ash residue produced by incineration. Such incinerator ashes will have to be disposed of in HW landfills. The Navy is thus evaluating methods of treatment of such ash to remove or immobilize the toxic constituents that persist following incineration in order to render the waste treatment residue nonhazardous. Appropriate technology identified in this work can be applied to ash produced by HW combuster operated by the Navy, if any, or be required for ash produced by commercial generators handling Navy HWs.

  15. Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility

    SciTech Connect (OSTI)

    Not Available

    1993-08-01T23:59:59.000Z

    The 200 Area Effluent Treatment Facility Dangerous Waste Permit Application documentation consists of both Part A and a Part B permit application documentation. An explanation of the Part A revisions associated with this treatment and storage unit, including the current revision, is provided at the beginning of the Part A section. Once the initial Hanford Facility Dangerous Waste Permit is issued, the following process will be used. As final, certified treatment, storage, and/or disposal unit-specific documents are developed, and completeness notifications are made by the US Environmental Protection Agency and the Washington State Department of Ecology, additional unit-specific permit conditions will be incorporated into the Hanford Facility Dangerous Waste Permit through the permit modification process. All treatment, storage, and/or disposal units that are included in the Hanford Facility Dangerous Waste Permit Application will operate under interim status until final status conditions for these units are incorporated into the Hanford Facility Dangerous Waste Permit. The Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility contains information current as of May 1, 1993.

  16. Non-Thermal Treatment of Hanford Site Low-Level Mixed Waste

    SciTech Connect (OSTI)

    NONE

    1998-09-01T23:59:59.000Z

    DOE proposes to transport contact-handled LLMW from the Hanford Site to the Allied Technology Group (ATG) Mixed Waste Facility (MWF) in Richland, Washington, for non-thermal treatment and to return the treated waste to the Hanford Site for eventual land disposal. Over a 3-year period the waste would be staged to the ATG MWF, and treated waste would be returned to the Hanford Site. The ATG MWF would be located on an 18 hectare (ha) (45 acre [at]) ATG Site adjacent to ATG's licensed low-level waste processing facility at 2025 Battelle Boulevard. The ATG MWF is located approximately 0.8 kilometers (km) (0.5 miles [mi]) south of Horn Rapids Road and 1.6 km (1 mi) west of Stevens Drive. The property is located within the Horn Rapids triangle in northern Richland (Figure 2.1). The ATG MWF is to be located on the existing ATG Site, near the DOE Hanford Site, in an industrial area in the City of Richland. The effects of siting, construction, and overall operation of the MWF have been evaluated in a separate State Environmental Policy Act (SEPA) EIS (City of Richland 1998). The proposed action includes transporting the LLMW from the Hanford Site to the ATG Facility, non-thermal treatment of the LLMW at the ATG MWF, and transporting the waste from ATG back to the Hanford Site. Impacts fi-om waste treatment operations would be bounded by the ATG SEPA EIS, which included an evaluation of the impacts associated with operating the non-thermal portion of the MWF at maximum design capacity (8,500 metric tons per year) (City of Richland 1998). Up to 50 employees would be required for non-thermal treatment portion of the MWF. This includes 40 employees that would perform waste treatment operations and 10 support staff. Similar numbers were projected for the thermal treatment portion of the MWF (City of Richland 1998).

  17. EA-1106: Explosive Waste Treatment Facility at Site 300, Lawrence Livermore National Laboratory, San Joaquin County, California

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the proposal to build, permit, and operate the Explosive Waste Treatment Facility to treat explosive waste at the U.S. Department of Energy's Lawrence...

  18. Development of Advanced Electrochemical Emission Spectroscopy for Monitoring Corrosion in Simulated DOE Liquid Waste

    SciTech Connect (OSTI)

    Digby D. Macdonald; Brian M. Marx; Sejin Ahn; Julio de Ruiz; Balaji Soundararaja; Morgan Smith; and Wendy Coulson

    2008-01-15T23:59:59.000Z

    Various forms of general and localized corrosion represent principal threats to the integrity of DOE liquid waste storage tanks. These tanks, which are of a single wall or double wall design, depending upon their age, are fabricated from welded carbon steel and contain a complex waste-form comprised of NaOH and NaNO{sub 3}, along with trace amounts of phosphate, sulfate, carbonate, and chloride. Because waste leakage can have a profound environmental impact, considerable interest exists in predicting the accumulation of corrosion damage, so as to more effectively schedule maintenance and repair. The different tasks that are being carried out under the current program are as follows: (1) Theoretical and experimental assessment of general corrosion of iron/steel in borate buffer solutions by using electrochemical impedance spectroscopy (EIS), ellipsometry and XPS techniques; (2) Development of a damage function analysis (DFA) which would help in predicting the accumulation of damage due to pitting corrosion in an environment prototypical of DOE liquid waste systems; (3) Experimental measurement of crack growth rate, acoustic emission signals and coupling currents for fracture in carbon and low alloy steels as functions of mechanical (stress intensity), chemical (conductivity), electrochemical (corrosion potential, ECP), and microstructural (grain size, precipitate size, etc) variables in a systematic manner, with particular attention being focused on the structure of the noise in the current and its correlation with the acoustic emissions; (4) Development of fracture mechanisms for carbon and low alloy steels that are consistent with the crack growth rate, coupling current data and acoustic emissions; (5) Inserting advanced crack growth rate models for SCC into existing deterministic codes for predicting the evolution of corrosion damage in DOE liquid waste storage tanks; (6) Computer simulation of the anodic and cathodic activity on the surface of the steel samples in order to exactly predict the corrosion mechanisms; (7) Wavelet analysis of EC noise data from steel samples undergoing corrosion in an environment similar to that of the high level waste storage containers, to extract data pertaining to general, pitting and stress corrosion processes, from the overall data. The Point Defect Model (PDM) is directly applied as the theoretical assessment method for describing the passive film formed on iron/steels. The PDM is used to describe general corrosion in the passive region of iron. In addition, previous work suggests that pit formation is due to the coalescence of cation vacancies at the metal/film interface which would make it possible to use the PDM parameters to predict the onset of pitting. This previous work suggests that once the critical vacancy density is reached, the film ruptures to form a pit. Based upon the kinetic parameters derived for the general corrosion case, two parameters relating to the cation vacancy formation and annihilation can be calculated. These two parameters can then be applied to predict the transition from general to pitting corrosion for iron/mild steels. If cation vacancy coalescence is shown to lead to pitting, it can have a profound effect on the direction of future studies involving the onset of pitting corrosion. The work has yielded a number of important findings, including an unequivocal demonstration of the role of chloride ion in passivity breakdown on nickel in terms of cation vacancy generation within the passive film, the first detection and characterization of individual micro fracture events in stress corrosion cracking, and the determination of kinetic parameters for the generation and annihilation of point defects in the passive film on iron. The existence of coupling between the internal crack environment and the external cathodic environment, as predicted by the coupled environment fracture model (CEFM), has also been indisputably established for the AISI 4340/NaOH system. It is evident from the studies that analysis of coupling current noise is a very sensitive tool f

  19. Hanford Site Secondary Waste Roadmap

    SciTech Connect (OSTI)

    Westsik, Joseph H.

    2009-01-29T23:59:59.000Z

    Summary The U.S. Department of Energy (DOE) is making plans to dispose of 54 million gallons of radioactive tank wastes at the Hanford Site near Richland, Washington. The high-level wastes and low-activity wastes will be vitrified and placed in permanent disposal sites. Processing of the tank wastes will generate secondary wastes, including routine solid wastes and liquid process effluents, and these need to be processed and disposed of also. The Department of Energy Office of Waste Processing sponsored a meeting to develop a roadmap to outline the steps necessary to design the secondary waste forms. Representatives from DOE, the U.S. Environmental Protection Agency, the Washington State Department of Ecology, the Oregon Department of Energy, Nuclear Regulatory Commission, technical experts from the DOE national laboratories, academia, and private consultants convened in Richland, Washington, during the week of July 21-23, 2008, to participate in a workshop to identify the risks and uncertainties associated with the treatment and disposal of the secondary wastes and to develop a roadmap for addressing those risks and uncertainties. This report describes the results of the roadmap meeting in Richland. Processing of the tank wastes will generate secondary wastes, including routine solid wastes and liquid process effluents. The secondary waste roadmap workshop focused on the waste streams that contained the largest fractions of the 129I and 99Tc that the Integrated Disposal Facility risk assessment analyses were showing to have the largest contribution to the estimated IDF disposal impacts to groundwater. Thus, the roadmapping effort was to focus on the scrubber/off-gas treatment liquids with 99Tc to be sent to the Effluent Treatment Facility for treatment and solidification and the silver mordenite and carbon beds with the captured 129I to be packaged and sent to the IDF. At the highest level, the secondary waste roadmap includes elements addressing regulatory and performance requirements, waste composition, preliminary waste form screening, waste form development, process design and support, and validation. The regulatory and performance requirements activity will provide the secondary waste-form performance requirements. The waste-composition activity will provide workable ranges of secondary waste compositions and formulations for simulants and surrogates. Preliminary waste form screening will identify candidate waste forms for immobilizing the secondary wastes. The waste form development activity will mature the waste forms, leading to a selected waste form(s) with a defensible understanding of the long-term release rate and input into the critical decision process for a secondary waste treatment process/facility. The process and design support activity will provide a reliable process flowsheet and input to support a robust facility design. The validation effort will confirm that the selected waste form meets regulatory requirements. The final outcome of the implementation of the secondary waste roadmap is the compliant, effective, timely, and cost-effective disposal of the secondary wastes. The work necessary to address the programmatic, regulatory, and technical risks and uncertainties identified through the Secondary Waste Roadmap Workshop are assembled into several program needs elements. Programmatic/Regulatory needs include: • Select and deploy Hanford tank waste supplemental treatment technology • Provide treatment capability for secondary waste streams from tank waste treatment • Develop consensus on secondary waste form acceptance. Technology needs include: • Define secondary waste composition ranges and uncertainties • Identify and develop waste forms for secondary waste immobilization and disposal • Develop test methods to characterize secondary waste form performance. Details for each of these program elements are provided.

  20. Advanced Mixed Waste Treatment Project melter system preliminary design technical review meeting

    SciTech Connect (OSTI)

    Eddy, T.L.; Raivo, B.D.; Soelberg, N.R.; Wiersholm, O.

    1995-02-01T23:59:59.000Z

    The Idaho National Engineering Laboratory Advanced Mixed Waste Treatment Project sponsored a plasma are melter technical design review meeting to evaluate high-temperature melter system configurations for processing heterogeneous alpha-contaminated low-level radioactive waste (ALLW). Thermal processing experts representing Department of Energy contractors, the Environmental Protection Agency, and private sector companies participated in the review. The participants discussed issues and evaluated alternative configurations for three areas of the melter system design: plasma torch melters and graphite arc melters, offgas treatment options, and overall system configuration considerations. The Technical Advisory Committee for the review concluded that graphite arc melters are preferred over plasma torch melters for processing ALLW. Initiating involvement of stakeholders was considered essential at this stage of the design. For the offgas treatment system, the advisory committee raised the question whether to a use wet-dry or a dry-wet system. The committee recommended that the waste stream characterization, feed preparation, and the control system are essential design tasks for the high-temperature melter treatment system. The participants strongly recommended that a complete melter treatment system be assembled to conduct tests with nonradioactive surrogate waste material. A nonradioactive test bed would allow for inexpensive design and operational changes prior to assembling a system for radioactive waste treatment operations.

  1. Development and status of the AL Mixed Waste Treatment Plan or I love that mobile unit of mine

    SciTech Connect (OSTI)

    Bounini, L. [USDOE Grand Junction Project Office, CO (United States); Williams, M. [USDOE Albuquerque Operations Office, NM (United States); Zygmunt, S. [Los Alamos National Lab., NM (United States)

    1995-02-01T23:59:59.000Z

    Nine Department of Energy (DOE) sites reporting to the Albuquerque Office (AL) have mixed waste that is chemically hazardous and radioactive. The hazardous waste regulations require the chemical portion of mixed waste to be to be treated to certain standards. The total volume of low-level mixed waste at the nine sites is equivalent to 7,000 drums, with individual site volumes ranging from 1 gallon of waste at the Pinellas Plant to 4,500 drums at Los Alamos National Laboratory. Nearly all the sites have a diversity of wastes requiring a diversity of treatment processes. Treatment capacity does not exist for much of this waste, and it would be expensive for each site to build the diversity of treatment processes needed to treat its own wastes. DOE-AL assembled a team that developed the AL Mixed Waste Treatment Plan that uses the resources of the nine sites to treat the waste at the sites. Work on the plan started in October 1993, and the plan was finalized in March 1994. The plan uses commercial treatment, treatability studies, and mobile treatment units. The plan specifies treatment technologies that will be built as mobile treatment units to be moved from site to site. Mobile units include bench-top units for very small volumes and treatability studies, drum-size units that treat one drum per day, and skid-size units that handle multiple drum volumes. After the tools needed to treat the wastes were determined, the sites were assigned to provide part of the treatment capacity using their own resources and expertise. The sites are making progress on treatability studies, commercial treatment, and mobile treatment design and fabrication. To date, this is the only plan for treating waste that brings the resources of several DOE sites together to treat mixed waste. It is the only program actively planning to use mobile treatment coordinated between DOE sites.

  2. Radioactive Waste Radioactive Waste

    E-Print Network [OSTI]

    Slatton, Clint

    form · Separate liquid from solid · Radionuclide · Separate all but H3/C14 #12;#12;Radioactive Waste;Radioactive Waste H3/C14 solids Type B (non-incinerable) metal glass hazardous materials #12;#12;Radioactive#12;Radioactive Waste at UF Bldg 831 392-8400 #12;Radioactive Waste · Program is designed to

  3. Secondary Waste Form Down-Selection Data Package—Fluidized Bed Steam Reforming Waste Form

    SciTech Connect (OSTI)

    Qafoku, Nikolla; Westsik, Joseph H.; Strachan, Denis M.; Valenta, Michelle M.; Pires, Richard P.

    2011-09-12T23:59:59.000Z

    The Hanford Site in southeast Washington State has 56 million gallons of radioactive and chemically hazardous wastes stored in 177 underground tanks (ORP 2010). The U.S. Department of Energy (DOE), Office of River Protection (ORP), through its contractors, is constructing the Hanford Tank Waste Treatment and Immobilization Plant (WTP) to convert the radioactive and hazardous wastes into stable glass waste forms for disposal. Within the WTP, the pretreatment facility will receive the retrieved waste from the tank farms and separate it into two treated process streams. These waste streams will be vitrified, and the resulting waste canisters will be sent to offsite (high-level waste [HLW]) and onsite (immobilized low-activity waste [ILAW]) repositories. As part of the pretreatment and ILAW processing, liquid secondary wastes will be generated that will be transferred to the Effluent Treatment Facility (ETF) on the Hanford Site for further treatment. These liquid secondary wastes will be converted to stable solid waste forms that will be disposed of in the Integrated Disposal Facility (IDF). To support the selection of a waste form for the liquid secondary wastes from WTP, Washington River Protection Solutions (WRPS) has initiated secondary waste form testing work at Pacific Northwest National Laboratory (PNNL). In anticipation of a down-selection process for a waste form for the Solidification Treatment Unit to be added to the ETF, PNNL is developing data packages to support that down-selection. The objective of the data packages is to identify, evaluate, and summarize the existing information on the four waste forms being considered for stabilizing and solidifying the liquid secondary wastes. At the Hanford Site, the FBSR process is being evaluated as a supplemental technology for treating and immobilizing Hanford LAW radioactive tank waste and for treating secondary wastes from the WTP pretreatment and LAW vitrification processes.

  4. Mixed Waste Treatment Using the ChemChar Thermolytic Detoxification Technique

    SciTech Connect (OSTI)

    Kuchynka, D.J.

    1997-01-01T23:59:59.000Z

    This R and D program addresses the treatment of mixed waste employing the ChemChar Thermolytic Detoxification process. Surrogate mixed waste streams will be treated in a four inch diameter, continuous feed, adiabatic reactor with the goal of meeting all regulatory treatment levels for the contaminants in the surrogates with the concomitant production of contaminant free by-products. Successful completion of this program will show that organic contaminants in mixed waste surrogates will be converted to a clean, energy rich synthesis gas capable of being used, without further processing, for power or heat generation. The inorganic components in the surrogates will be found to be adsorbed on a macroporous coal char activated carbon substrate which is mixed with the waste prior to treatment. These contaminants include radioactive metal surrogate species, RCRA hazardous metals and any acid gases formed during the treatment process. The program has three main tasks that will be performed to meet the above objectives. The first task is the design and construction of the four inch reactor at Mirage Systems in Sunnyvale, CA. The second task is production and procurement of the activated carbon char employed in the ChemChartest runs and identification of two surrogate mixed wastes. The last task is testing and operation of the reactor on char/surrogate waste mixtures to be performed at the University of Missouri. The deliverables for the project are a Design Review Report, Operational Test Plan, Topical Report and Final Report. This report contains only the results of the design and construction carbon production-surrogate waste identification tasks.Treatment of the surrogate mixed wastes has just begun and will not be reported in this version of the Final Report. The latter will be reported in the final version of the Final Report.

  5. Integrated demonstration of molten salt oxidation with salt recycle for mixed waste treatment

    SciTech Connect (OSTI)

    Hsu, P.C.

    1997-11-01T23:59:59.000Z

    Molten Salt Oxidation (MSO) is a thermal, nonflame process that has the inherent capability of completely destroying organic constituents of mixed wastes, hazardous wastes, and energetic materials while retaining inorganic and radioactive constituents in the salt. For this reason, MSO is considered a promising alternative to incineration for the treatment of a variety of organic wastes. Lawrence Livermore National Laboratory (LLNL) has prepared a facility and constructed an integrated pilot-scale MSO treatment system in which tests and demonstrations are performed under carefully controlled (experimental) conditions. The system consists of a MSO processor with dedicated off-gas treatment, a salt recycle system, feed preparation equipment, and equipment for preparing ceramic final waste forms. This integrated system was designed and engineered based on laboratory experience with a smaller engineering-scale reactor unit and extensive laboratory development on salt recycle and final forms preparation. In this paper we present design and engineering details of the system and discuss its capabilities as well as preliminary process demonstration data. A primary purpose of these demonstrations is identification of the most suitable waste streams and waste types for MSO treatment.

  6. Continuous mercury monitor for thermal treatment and waste-to-energy operations

    SciTech Connect (OSTI)

    Schlager, R.J.; Wilson, K.G.; Sappey, A.D.; Anderson, G.L.; Sagan, F.J. [ADA Technologies, Inc., Englewood, CO (United States)

    1996-12-31T23:59:59.000Z

    Treating wastes by thermal means offers benefits in terms of reducing waste volumes and in recovering energy values from the wastes. Thermal treatment has been an effective technology for a number of years, and is being used more in the US. Significant sources of waste in the US are municipal solid waste, hospital wastes, hazardous wastes, and wastes generated form the DOE complex. Mercury is found in these wastes and is emitted as a pollutant from sources that treat these materials thermally. Because of mercury`s toxicity, there is a considerable amount of activity aimed at its regulation and control. One of the key elements to effectively control the release of mercury is the ability to continuously monitor its concentration from emitting sources. ADA Technologies is developing a continuous monitoring system for measuring these emissions in real time. A real-time analyzer will assure that compliance limits are met and that emissions are kept as low as possible. Because mercury is emitted from sources in several different forms, such as elemental mercury and mercuric chloride, provisions have been incorporated in the analyzer that will allow for the measurement of all mercury compounds. The system will provide a number of advantages over existing test methods: (1) it will provide a real-time measure of emissions rates; (2) it will assure facility operators, regulators, and the public that emissions control systems are working at peak efficiency; and (3) it will provide information as to the nature of the emitted mercury (elemental mercury or speciated compounds).

  7. Development of Advanced Electrochemical Emission Spectroscopy for Monitoring Corrosion in Simulated DOE Liquid Waste

    SciTech Connect (OSTI)

    Digby Macdonald; Brian Marx; Balaji Soundararajan; Morgan Smith

    2005-07-28T23:59:59.000Z

    The different tasks that have been carried out under the current program are as follows: (1) Theoretical and experimental assessment of general corrosion of iron/steel in borate buffer solutions by using electrochemical impedance spectroscopy (EIS), ellipsometry and XPS techniques; (2) Development of a damage function analysis (DFA), which would help in predicting the accumulation of damage due to pitting corrosion in an environment prototypical of DOE liquid waste systems; (3) Experimental measurement of crack growth rate, acoustic emission signals, and coupling currents for fracture in carbon and low alloy steels as functions of mechanical (stress intensity), chemical (conductivity), electrochemical (corrosion potential, ECP), and microstructural (grain size, precipitate size, etc) variables in a systematic manner, with particular attention being focused on the structure of the noise in the current and its correlation with the acoustic emissions; (4) Development of fracture mechanisms for carbon and low alloy steels that are consistent with the crack growth rate, coupling current data and acoustic emissions; (5) Inserting advanced crack growth rate models for SCC into existing deterministic codes for predicting the evolution of corrosion damage in DOE liquid waste storage tanks; (6) Computer simulation of the anodic and cathodic activity on the surface of the steel samples in order to exactly predict the corrosion mechanisms; (7) Wavelet analysis of EC noise data from steel samples undergoing corrosion in an environment similar to that of the high level waste storage containers, to extract data pertaining to general, pitting and stress corrosion processes, from the overall data. The work has yielded a number of important findings, including an unequivocal demonstration of the role of chloride ion in passivity breakdown on nickel in terms of cation vacancy generation within the passive film, the first detection and characterization of individual micro fracture events in stress corrosion cracking, and the determination of kinetic parameters for the generation and annihilation of point defects in the passive film on iron. The existence of coupling between the internal crack environment and the external cathodic environment, as predicted by the coupled environment fracture model (CEFM), has also been indisputably established for the AISI 4340/NaOH system. It is evident from the studies that analysis of coupling current noise is a very sensitive tool for studying the crack tip processes in relation to the chemical, mechanical, electrochemical, and microstructural properties of the system. Experiments are currently being carried out to explore these crack tip processes by simultaneous measurement of the acoustic activity at the crack tip in an effort to validate the coupling current data. These latter data are now being used to deterministically predict the accumulation of general and localized corrosion damage on carbon in prototypical DOE liquid waste storage tanks. Computer simulation of the cathodic and anodic activity on the steel surfaces is also being carried out in an effort to simulate the actual corrosion process. Wavelet analysis of the coupling current data promises to be a useful tool to differentiate between the different corrosion mechanisms. Hence, wavelet analysis of the coupling current data from the DOE waste containers is also being carried out to extract data pertaining to general, pitting and stress corrosion processes, from the overall data which is bound to contain noise fluctuations due to any or all of the above mentioned processes.

  8. Surfactants containing radioactive run-offs: Ozone treatment, influence on nuclear power plants water waste special treatment

    SciTech Connect (OSTI)

    Prokudina, S.A.; Grachok, M.A. [Belarussian State Economic Univ., Minsk (Belarus)

    1993-12-31T23:59:59.000Z

    The authors discuss the problems encountered in the efficiency of radioactive waste treatment in nuclear power plants in Kursk. The ozonization of aqueous solutions of surfactants was carried out in the laboratory`s ozonization system. The surfactants which are discharged to the ion exchangers deteriorate resins, clog up the ion exchangers, and decrease filtration velocity. Therefore, this investigation focused on finding a method to increase the efficiency of this treatment process.

  9. The treatment of wood preserving wastes with activated carbon

    E-Print Network [OSTI]

    Pence, Robert Fuller

    1978-01-01T23:59:59.000Z

    requirement and treatment schemes should be based on these combined requirements. Current treatment schemes employed in the wood preserving industry combine physical, chemical, and biological processes and operations in treating wastewaters. Jones, et al...-five of the plants performed secondary treatment on-site of which 32 used biological methods. Only 6 per- cent discharged their wastewaters directly to the environment without any form of treatment and approximately 40 percent of the plants planned to change...

  10. Surveillance and maintenance plan for the inactive liquid low-level waste tanks at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Not Available

    1994-11-01T23:59:59.000Z

    ORNL has a total of 54 inactive liquid low-level waste (ILLLW) tanks. In the past, these tanks were used to contain radioactive liquid wastes from various research programs, decontamination operations, and reactor operations. The tanks have since been removed from service for various reasons; the majority were retired because of their age, some due to integrity compromises, and others because they did not meet the current standards set by the Federal Facilities Agreement (FFA). Many of the tanks contain residual radioactive liquids and/or sludges. Plans are to remediate all tanks; however, until remediation of each tank, this Surveillance and Maintenance (S&M) Plan will be used to monitor the safety and inventory containment of these tanks.

  11. TREATMENT OF METAL-LADEN HAZARDOUS WASTES WITH ADVANCED CLEAN COAL TECHNOLOGY BY-PRODUCTS

    SciTech Connect (OSTI)

    James T. Cobb, Jr.

    2003-09-12T23:59:59.000Z

    Metal-laden wastes can be stabilized and solidified using advanced clean coal technology by-products (CCTBs)--fluid bed combustor ash and spray drier solids. These utility-generated treatment chemicals are available for purchase through brokers, and commercial applications of this process are being practiced by treaters of metal-laden hazardous waste. A complex of regulations governs this industry, and sensitivities to this complex has discouraged public documentation of treatment of metal-laden hazardous wastes with CCTBs. This report provides a comprehensive public documentation of laboratory studies that show the efficacy of the stabilization and solidification of metal-laden hazardous wastes--such as lead-contaminated soils and sandblast residues--through treatment with CCTBs. It then describes the extensive efforts that were made to obtain the permits allowing a commercial hazardous waste treater to utilize CCTBs as treatment chemicals and to install the equipment required to do so. It concludes with the effect of this lengthy process on the ability of the treatment company to realize the practical, physical outcome of this effort, leading to premature termination of the project.

  12. Integrated process analysis of treatment systems for mixed low level waste

    SciTech Connect (OSTI)

    Cooley, C.R. [Dept. of Energy, Washington, DC (United States); Schwinkendorf, W.E. [Lockheed Martin Idaho Technology Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.]|[Sandia National Labs., Albuquerque, NM (United States); Bechtold, T.E. [Lockheed Martin Idaho Technology Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.

    1997-10-01T23:59:59.000Z

    Selection of technologies to be developed for treatment of DOE`s mixed low level waste (MLLW) requires knowledge and understanding of the expected costs, schedules, risks, performance, and reliability of the total engineered systems that use these technologies. Thus, an integrated process analysis program was undertaken to identify the characteristics and needs of several thermal and nonthermal systems. For purposes of comparison, all systems were conceptually designed for a single facility processing the same amount of waste at the same rate. Thirty treatment systems were evaluated ranging from standard incineration to innovative thermal systems and innovative nonthermal chemical treatment. Treating 236 million pounds of waste in 20 years through a central treatment was found to be the least costly option with total life cycle cost ranging from $2.1 billion for a metal melting system to $3.9 billion for a nonthermal acid digestion system. Little cost difference exists among nonthermal systems or among thermal systems. Significant cost savings could be achieved by working towards maximum on line treatment time per year; vitrifying the final waste residue; decreasing front end characterization segregation and sizing requirements; using contaminated soil as the vitrifying agent; and delisting the final vitrified waste form from Resource Conservation and Recovery Act (RCRA) Land Disposal Restriction (LDR) requirements.

  13. Mixed Waste Treatment Project: LLNL and LANL computer simulations of integrated flowsheets

    SciTech Connect (OSTI)

    Camp, D.W.; Dietsche, L.J.; Upadhye, R.S. [Lawrence Livermore National Lab., CA (United States); Borduin, L.C.; Pendergrass, J.A. [Los Alamos National Lab., NM (United States); Thompson, T.K. [Thompson (T.K.), Inc., Los Alamos, NM (United States)

    1994-03-01T23:59:59.000Z

    Computer simulations of mixed waste processing flowsheets using ASPEN PLUS process simulation software were completed by a joint Lawrence Livermore National Laboratory/Los National Laboratory (LLNL/LANL) effort for the US Department of Energy Mixed Waste Treatment Project. The LLNL model used relatively detailed synthesized chemical ``cocktails`` to simulate waste streams. The LANL approach used less detail but made extensive use of simple steam splitters and thermodynamic coal models for combustible waste compositions. The two modeling approaches agreed within 16% for the product streams and within 25% for the auxiliary fuel rate. The discrepancy between the auxiliary fuel rates was traced to different methods of handling organics in lab packs and scintillation vials with the process models. The ASPEN models are valuable tools for evaluating waste processing flowsheets.

  14. Independent peer review panel report on the integrated nonthermal treatment systems study and the comparison of integrated thermal and integrated nonthermal treatment systems for mixed low level waste

    SciTech Connect (OSTI)

    NONE

    1996-08-01T23:59:59.000Z

    The US Department of Energy`s (DOE) Office of Environmental Management (EM) Office of Science and Technology (OST) has conducted studies of integrated thermal treatment systems and integrated nonthermal treatment systems (INTS) for treating contact handled, alpha and non-alpha mixed low level radioactive waste (MLLW). The MLLW in the DOE complex consists of a wide variety of organic and inorganic solids and liquids contaminated with radioactive substances. Treatment systems are needed to destroy organic material and stabilize residues prior to land disposal. In May 1996 the Deputy Assistant Secretary for OST appointed an Independent Peer Review Panel to: (1) review and comment on the INTS Study; (2) make recommendations on the most promising thermal and nonthermal treatment systems; (3) make recommendations on research and development necessary to prove the performance of nonthermal and thermal technologies; and (4) review and comment on the preliminary draft of the ITTS/INTS Comparison Report. This report presents the primary conclusions and recommendations based on the review of the INTS study and the comparison report. System selection, overviews, comparisons, cost estimations and sensitivity analyses, and recommended R and D engineering needs are then described and discussed.

  15. Design report on the test system used to assess treatment of trench water from Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

    SciTech Connect (OSTI)

    Kent, T.E.; Taylor, P.A.

    1992-09-01T23:59:59.000Z

    New liquid waste streams will be generated as a consequence of closure activities at Waste Area Grouping (WAG) 6 at Oak Ridge National Laboratory (ORNL). It is proposed that these waste streams be treated for removal of contaminants by adding them to the ORNL wastewater treatment facilities. Previous bench-scale treatability studies indicate that ORNL treatment operations will adequately remove the contaminants, although additional study is required to characterize the secondary waste materials produced as a result of the treatment. A larger scale treatment system was constructed to produce secondary wastes in the quantities necessary for characterization and US Environmental protection Agency toxicity characteristic leaching procedure (TCLP) testing. The test system is designed to simulate the operation of the ORNL process waste treatment facilities and to treat a mixture of ORNL process wastewater and WAG 6 wastewater at a combined flow rate of 0.5 L/min. The system is designed to produce the necessary quantities of waste sludges and spent carbon for characterization studies and TCLP testing.

  16. Mixed-waste treatment -- What about the residuals? A comparative analysis of MSO and incineration

    SciTech Connect (OSTI)

    NONE

    1993-06-01T23:59:59.000Z

    This report examines the issues concerning final waste forms, or residuals, that result from the treatment of mixed waste in molten salt oxidation (MSO) and incinerator systems. MSO is a technology with the potential to treat a certain segment of the waste streams at US Department of Energy (DOE) sites. MSO was compared with incineration because incineration is the best demonstrated available technology (BDAT) for the same waste streams. The Grand Junction Projects Office (GJPO) and Oak Ridge National Laboratory (ORNL) prepared this report for the DOE Office of Environmental Restoration (OER). The goals of this study are to objectively evaluate the anticipated residuals from MSO and incineration, examine regulatory issues for these final waste forms, and determine secondary treatment options. This report, developed to address concerns that MSO residuals present unique disposal difficulties, is part of a larger effort to successfully implement MSO as a treatment technology for mixed and hazardous waste. A Peer Review Panel reviewed the MSO technology in November 1991, and the implementation effort is ongoing under the guidance of the MSO Task Force.

  17. Treatment of M-area mixed wastes at the Savannah River Site

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    The Department of Energy has prepared this environmental assessment, DOE/EA-0918, to assess the potential environmental impacts of the treatment of mixed wastes currently stored in the M-Area at the Savannah River Site, near Aiken, South Carolina. DOE is proposing to treat and stabilize approximately 700,000 gallons of mixed waste currently stored in the Interim Treatment/Storage Facility (IT/SF) and Mixed Waste Storage Shed (MWSS). This waste material is proposed to be stabilized using a vitrification process and temporarily stored until final disposal is available by the year 2005. This document has been prepared to assess the potential environmental impacts attributable to the treatment and stabilization of M-area mixed wastes, the closure of the interim storage area, and storage of the vitrified waste until disposal in onsite RCRA vaults. Based on the analyses in the environmental assessment, the Department of Energy has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, the preparation of an environmental impact statement is not required, and the Department of Energy is issuing this finding of no significant impact.

  18. Characterization of oil and gas waste disposal practices and assessment of treatment costs. Yearly report, July 1, 1992--June 30, 1993

    SciTech Connect (OSTI)

    Bedient, P.B.

    1993-07-30T23:59:59.000Z

    The project consists of 3 tasks: (1) Developing a Production Environmental Database (PED) with the purpose of investigating the current industry waste storage and disposal practices by different regions, states and types of waste and investigating the environmental impacts associated with these practices; (2) Evaluating the suitability of available and developing technologies for treating produced water and identifying applicable unit process configurations; and (3) Evaluating the costs associated with various degrees of treatment achievable by different configurations. Records of wells drilled during the years 1986 through 1991 were compiled from industry reports. Overall, drilling has decreased from an average of 60,000 wells/yr for the period 1981 through 1985 to 20,000/yr during 1986 through 1991. A produced water database was developed from data and information provided by the various state and federal agencies. Currently, the database has information on the production of oil, gas and brines from 24 states. The data from the produced water database indicate that for the most part, Class II Injection seemed to be the common disposal method. Other methods included evaporation, surface disposal via NPDES permit, road spreading, hauling out-of-state, and annular disposal. A survey of oil and gas operators has been developed, reviewed and edited. The survey is divided-by topic into three sections. (1) drilling wastes; (2) associated wastes; and (3) produced water. The objective of the survey is to develop more current information on the waste volumes and disposal methods used during 1986 through 1991. The possible treatment scenarios for produced water have been identified. Organic and inorganic contaminant removal, liquid/solid separation and liquid/emulsified oil separation have been identified as the main objectives of the treatment of produced water.

  19. Future waste treatment and energy systems – examples of joint scenarios

    SciTech Connect (OSTI)

    Münster, M., E-mail: maem@dtu.dk [System Analysis Division, DTU Management Engineering, Technical University of Denmark, Frederiksborgvej 399, 4000 Roskilde (Denmark); Finnveden, G. [KTH Royal Institute of Technology, School of Architecture and the Built Environment, Department of Planning and Environment, Division of Environmental Strategies Research – fms, 100 44 Stockholm (Sweden); Wenzel, H. [Institute of Chemical Engineering, Biotechnology and Environmental Technology, University of Southern Denmark, Niels Bohrs Allé 1, 5230 Odense M (Denmark)

    2013-11-15T23:59:59.000Z

    Highlights: • Approach for use of scenarios dealing with both waste management and energy issues. • Overall scenarios for the common project and sub-scenarios in parts of the project. • Combining different types of scenarios to the tools of different disciplines. • Use of explorative external scenarios based on marginals for consequential LCA. - Abstract: Development and use of scenarios for large interdisciplinary projects is a complicated task. This article provides practical examples of how it has been carried out in two projects addressing waste management and energy issues respectively. Based on experiences from the two projects, recommendations are made for an approach concerning development of scenarios in projects dealing with both waste management and energy issues. Recommendations are given to develop and use overall scenarios for the project and leave room for sub-scenarios in parts of the project. Combining different types of scenarios is recommended, too, in order to adapt to the methods and tools of different disciplines, such as developing predictive scenarios with general equilibrium tools and analysing explorative scenarios with energy system analysis tools. Furthermore, as marginals identified in differing future background systems determine the outcomes of consequential life cycle assessments (LCAs), it is considered advisable to develop and use explorative external scenarios based on possible marginals as a framework for consequential LCAs. This approach is illustrated using an on-going Danish research project.

  20. HWMA/RCRA Closure Plan for the CPP-648 Radioactive Solid and Liquid Waste Storage Tank System (VES-SFE-106)

    SciTech Connect (OSTI)

    S. K. Evans

    2006-08-15T23:59:59.000Z

    This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan for the Radioactive Solid and Liquid Waste Storage Tank System located in the adjacent to the Sludge Tank Control House (CPP-648), Idaho Nuclear Technology and Engineering Center, Idaho National Laboratory, was developed to meet the interim status closure requirements for a tank system. The system to be closed includes a tank and associated ancillary equipment that were determined to have managed hazardous waste. The CPP-648 Radioactive Solid and Liquid Waste Storage Tank System will be "cleaned closed" in accordance with the requirements of the Hazardous Waste Management Act/Resource Conservation and Recovery Act as implemented by the Idaho Administrative Procedures Act and 40 Code of Federal Regulations 265. This closure plan presents the closure performance standards and methods of acheiving those standards for the CPP-648 Radioactive Solid and Liquid Waste Storage Tank System.

  1. Comparison of costs for alternative mixed low-level waste treatment systems

    SciTech Connect (OSTI)

    Schwinkendorf, W.E.; Harvego, L. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); Cooley, C.R. [Dept. of Energy (United States); Biagi, C. [Morrison Knudsen (United States)

    1996-12-31T23:59:59.000Z

    Total life cycle costs (TLCCs), including disposal costs, of thermal, nonthermal and enhanced nonthermal systems were evaluated to guide future research and development programs for the treatment of mixed low-level waste (MLLW) consisting of RCRA hazardous and low-level radioactive wastes. In these studies, nonthermal systems are defined as those systems that process waste at temperatures less than 350 C. Preconceptual designs and costs were developed for thirty systems with a capacity (2,927 lbs/hr) to treat the DOE MLLW stored inventor y(approximately 236 million pounds) in 20 years in a single, centralized facility. A limited comparison of the studies` results is presented in this paper. Sensitivity of treatment costs with respect to treatment capacity, number of treatment facilities, and system availability were also determined. The major cost element is operations and maintenance (O and M), which is 50 to 60% of the TLCC for both thermal and nonthermal systems. Energy costs constitute a small fraction (< 1%) of the TLCCs. Equipment cost is only 3 to 5% of the treatment cost. Evaluation of subsystem costs demonstrate that receiving and preparation is the highest cost subsystem at about 25 to 30% of the TLCC for both thermal and nonthermal systems. These studies found no cost incentives to use nonthermal or hybrid (combined nonthermal treatment with stabilization by vitrification) systems in place of thermal systems. However, there may be other incentives including fewer air emissions and less local objection to a treatment facility. Building multiple treatment facilities to treat the same total mass of waste as a single facility would increase the total treatment cost significantly, and improved system availability decreases unit treatment costs by 17% to 30%.

  2. DESIGN OF THE DEMOSNTRATION BULK VITRIFICATION SYSTEM FOR THE SUPPLEMENTAL TREATMENT OF LOW ACTIVITY TANK WASTE AT HANFORD

    SciTech Connect (OSTI)

    VAN BEEK JE

    2008-02-14T23:59:59.000Z

    In June 2004, the Demonstration Bulk Vitrification System (DBVS) was initiated with the intent to design, construct, and operate a full-scale bulk vitrification pilot-plant to treat low-activity tank waste from Hanford Tank 241-S-109. The DBVS facility uses In-Container Vitrification{trademark} (ICV{trademark}) at the core of the treatment process. The basic process steps combine liquid low-activity waste (LAW) and glassformers; dry the mixture; and then vitrify the mixture in a batch feed-while-melt process in a refractory lined steel container. Off-gases are processed through a state-of-the-art air pollution control system including sintered-metal filtration, thermal oxidation, acid gas scrubbing, and high-efficiency particulate air (HEPA) and high-efficiency gas adsorber (HEGA) filtration. Testing has focused on development and validation of the waste dryer, ICV, and sintered-metal filters (SMFs) equipment, operations enhancements, and glass formulation. With a parallel testing and design process, testing has allowed improvements to the DBVS equipment configuration and operating methodology, since its original inception. Design improvements include optimization of refractory panels in the ICV, simplifying glassformer addition equipment, increasing the number of waste feed chutes to the ICV, and adding capability for remote clean-out of piping, In addition, the U.S. Department of Energy (DOE) has provided an independent review of the entire DBVS process. While the review did not find any fatal flaws, some technical issues were identified that required a re-evaluation of the DBVS design and subsequent changes to the design. A 100 percent design package for the pilot plant will be completed and submitted to DOE for review in early 2008 that incorporates process improvements substantiated through testing and reviews. This paper provides a description of the bulk vitrification process and a discussion of major equipment design changes that have occurred based on full-scale testing over the past two years and DOE reviews.

  3. Enterprise Assessments Operational Awareness Record, Waste Treatment and

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T,OfficeEnd of Year 2010 SNFEnergySession0-02 -Railroad Hazardous gthe Waste

  4. Waste Treatment Facility Passes Federal Inspection, Completes Final

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently20,000 Russian Nuclear Warheads|of Energy WashingtonWaste Isolation PilotMilestone,

  5. PILOT-SCALE TEST RESULTS OF A THIN FILM EVAPORATOR SYSTEM FOR MANAGEMENT OF LIQUID HIGH-LEVEL WASTES AT THE HANFORD SITE WASHINGTON USA -11364

    SciTech Connect (OSTI)

    CORBETT JE; TEDESCH AR; WILSON RA; BECK TH; LARKIN J

    2011-02-14T23:59:59.000Z

    A modular, transportable evaporator system, using thin film evaporative technology, is planned for deployment at the Hanford radioactive waste storage tank complex. This technology, herein referred to as a wiped film evaporator (WFE), will be located at grade level above an underground storage tank to receive pumped liquids, concentrate the liquid stream from 1.1 specific gravity to approximately 1.4 and then return the concentrated solution back into the tank. Water is removed by evaporation at an internal heated drum surface exposed to high vacuum. The condensed water stream will be shipped to the site effluent treatment facility for final disposal. This operation provides significant risk mitigation to failure of the aging 242-A Evaporator facility; the only operating evaporative system at Hanford maximizing waste storage. This technology is being implemented through a development and deployment project by the tank farm operating contractor, Washington River Protection Solutions (WRPS), for the Office of River Protection/Department of Energy (ORPIDOE), through Columbia Energy and Environmental Services, Inc. (Columbia Energy). The project will finalize technology maturity and install a system at one of the double-shell tank farms. This paper summarizes results of a pilot-scale test program conducted during calendar year 2010 as part of the ongoing technology maturation development scope for the WFE.

  6. Assessment of natural gas technology opportunities in the treatment of selected metals containing wastes. Topical report, June 1994-August 1995

    SciTech Connect (OSTI)

    McGervey, J.; Holmes, J.G.; Bluestein, J.

    1995-08-01T23:59:59.000Z

    The report analyzes the disposal of certain waste streams that contain heavy metals, as determined by Resource Conservation and Recovery Act (RCRA) regulations. Generation of the wastes, the regulatory status of the wastes, and current treatment practices are characterized, and the role of natural gas is determined. The four hazardous metal waste streams addressed in this report are electric arc furnace (EAF) dust, electroplating sludge wastes, used and off-specification circuit boards and cathode ray tubes, and wastes from lead manufacturing. This report assesses research and development opportunities relevant to natural gas technologies that may result from current and future enviromental regulations.

  7. Chemical hazards associated with treatment of waste electrical and electronic equipment

    SciTech Connect (OSTI)

    Tsydenova, Oyuna [Institute for Global Environmental Strategies, 2108-11 Kamiyamaguchi, Hayama, Kanagawa 240-0115 (Japan); Bengtsson, Magnus, E-mail: bengtsson@iges.or.jp [Institute for Global Environmental Strategies, 2108-11 Kamiyamaguchi, Hayama, Kanagawa 240-0115 (Japan)

    2011-01-15T23:59:59.000Z

    This review paper summarizes the existing knowledge on the chemical hazards associated with recycling and other end-of-life treatment options of waste electrical and electronic equipment (e-waste). The hazards arise from the presence of heavy metals (e.g., mercury, cadmium, lead, etc.), flame retardants (e.g., pentabromophenol, polybrominated diphenyl ethers (PBDEs), tetrabromobisphenol-A (TBBPA), etc.) and other potentially harmful substances in e-waste. If improperly managed, the substances may pose significant human and environmental health risks. The review describes the potentially hazardous content of e-waste, examines the existing e-waste management practices and presents scientific data on human exposure to chemicals, workplace and environmental pollution associated with the three major e-waste management options, i.e., recycling, incineration and landfilling. The existing e-waste management practices and associated hazards are reviewed separately for developed and developing countries. Finally, based on this review, the paper identifies gaps in the existing knowledge and makes some recommendations for future research.

  8. Re-refining of Waste Oil Solvent Is Used in Treatment/Distillation Process

    E-Print Network [OSTI]

    unknown authors

    INDUSTRIAL APPLICATION. A combination solvent treatment/distillation process has been designed for re-refining industrial waste oil (such as equipment lubricants, metal-working oil, and process oil) and used automotive lubricants (engine oil, hydraulic oil, and gear oil) for reuse. WASTE ENERGY RECOVERY. Recycling of waste oil in the United States has the potential to save the energy equivalent of 7-12 million bbl of crude oil annually.1 WASTE OIL RECOVERY. Prior to 1960, a significant portion of the demand for automotive lubricating oil was met by re-relined used oil. At the time, 150 re-refineries produced 300 million gal of motor oil annually. Since 1960, however, the production of re-refined oil has steadily declined. In 1981, for example, out of about 1.2 billion gal of automobile lubricating oil and 1.6 billion gal of industrial lubricating oils purchased, 25 U.S. rerefineries

  9. SAVANNAH RIVER SITE INCIPIENT SLUDGE MIXING IN RADIOACTIVE LIQUID WASTE STORAGE TANKS DURING SALT SOLUTION BLENDING

    SciTech Connect (OSTI)

    Leishear, R.; Poirier, M.; Lee, S.; Steeper, T.; Fowley, M.; Parkinson, K.

    2011-01-12T23:59:59.000Z

    This paper is the second in a series of four publications to document ongoing pilot scale testing and computational fluid dynamics (CFD) modeling of mixing processes in 85 foot diameter, 1.3 million gallon, radioactive liquid waste, storage tanks at Savannah River Site (SRS). Homogeneous blending of salt solutions is required in waste tanks. Settled solids (i.e., sludge) are required to remain undisturbed on the bottom of waste tanks during blending. Suspension of sludge during blending may potentially release radiolytically generated hydrogen trapped in the sludge, which is a safety concern. The first paper (Leishear, et. al. [1]) presented pilot scale blending experiments of miscible fluids to provide initial design requirements for a full scale blending pump. Scaling techniques for an 8 foot diameter pilot scale tank were also justified in that work. This second paper describes the overall reasons to perform tests, and documents pilot scale experiments performed to investigate disturbance of sludge, using non-radioactive sludge simulants. A third paper will document pilot scale CFD modeling for comparison to experimental pilot scale test results for both blending tests and sludge disturbance tests. That paper will also describe full scale CFD results. The final paper will document additional blending test results for stratified layers in salt solutions, scale up techniques, final full scale pump design recommendations, and operational recommendations. Specifically, this paper documents a series of pilot scale tests, where sludge simulant disturbance due to a blending pump or transfer pump are investigated. A principle design requirement for a blending pump is UoD, where Uo is the pump discharge nozzle velocity, and D is the nozzle diameter. Pilot scale test results showed that sludge was undisturbed below UoD = 0.47 ft{sup 2}/s, and that below UoD = 0.58 ft{sup 2}/s minimal sludge disturbance was observed. If sludge is minimally disturbed, hydrogen will not be released. Installation requirements were also determined for a transfer pump which will remove tank contents, and which is also required to not disturb sludge. Testing techniques and test results for both types of pumps are presented.

  10. Method and apparatus for treating gaseous effluents from waste treatment systems

    DOE Patents [OSTI]

    Flannery, Philip A. (Ramsey, MT); Kujawa, Stephan T. (Butte, MT)

    2000-01-01T23:59:59.000Z

    Effluents from a waste treatment operation are incinerated and oxidized by passing the gases through an inductively coupled plasmas arc torch. The effluents are transformed into plasma within the torch. At extremely high plasma temperatures, the effluents quickly oxidize. The process results in high temperature oxidation of the gases without addition of any mass flow for introduction of energy.

  11. CAST STONE TECHNOLOGY FOR THE TREATMENT AND IMMOBILIZATION OF LOW-ACTIVITY WASTE

    SciTech Connect (OSTI)

    MINWALL HJ

    2011-04-08T23:59:59.000Z

    Cast stone technology is being evaluated for potential application in the treatment and immobilization of Hanford low-activity waste. The purpose of this document is to provide background information on cast stone technology. The information provided in the report is mainly based on a pre-conceptual design completed in 2003.

  12. STATISTICAL SAMPLING FOR IN-SERVICE INSPECTION OF LIQUID WASTE TANKS AT THE SAVANNAH RIVER SITE

    SciTech Connect (OSTI)

    Harris, S.; Baxter, L.

    2011-04-07T23:59:59.000Z

    Savannah River Remediation, LLC (SRR) is implementing a statistical sampling strategy for In-Service Inspection (ISI) of Liquid Waste (LW) Tanks at the United States Department of Energy's Savannah River Site (SRS) in Aiken, South Carolina. As a component of SRS's corrosion control program, the ISI program assesses tank wall structural integrity through the use of ultrasonic testing (UT). The statistical strategy for ISI is based on the random sampling of a number of vertically oriented unit areas, called strips, within each tank. The number of strips to inspect was determined so as to attain, over time, a high probability of observing at least one of the worst 5% in terms of pitting and corrosion across all tanks. The probability estimation to determine the number of strips to inspect was performed using the hypergeometric distribution. Statistical tolerance limits for pit depth and corrosion rates were calculated by fitting the lognormal distribution to the data. In addition to the strip sampling strategy, a single strip within each tank was identified to serve as the baseline for a longitudinal assessment of the tank safe operational life. The statistical sampling strategy enables the ISI program to develop individual profiles of LW tank wall structural integrity that collectively provide a high confidence in their safety and integrity over operational lifetimes.

  13. RADIOACTIVE DEMONSTRATIONS OF FLUIDIZED BED STEAM REFORMING WITH ACUTAL HANFORD LOW ACTIVITY WASTES VERIFYING FBSR AS A SUPPLEMENTARY TREATMENT

    SciTech Connect (OSTI)

    Jantzen, C.; Crawford, C.; Burket, P.; Bannochie, C.; Daniel, G.; Nash, C.; Cozzi, A.; Herman, C.

    2012-01-12T23:59:59.000Z

    The U.S. Department of Energy's Office of River Protection is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level waste (HLW) and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the cleanup mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA). Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. Fluidized Bed Steam Reforming (FBSR) is one of the supplementary treatments being considered. FBSR offers a moderate temperature (700-750 C) continuous method by which LAW and other secondary wastes can be processed irrespective of whether they contain organics, nitrates/nitrites, sulfates/sulfides, chlorides, fluorides, and/or radio-nuclides like I-129 and Tc-99. Radioactive testing of Savannah River LAW (Tank 50) shimmed to resemble Hanford LAW and actual Hanford LAW (SX-105 and AN-103) have produced a ceramic (mineral) waste form which is the same as the non-radioactive waste simulants tested at the engineering scale. The radioactive testing demonstrated that the FBSR process can retain the volatile radioactive components that cannot be contained at vitrification temperatures. The radioactive and nonradioactive mineral waste forms that were produced by co-processing waste with kaolin clay in an FBSR process are shown to be as durable as LAW glass.

  14. Treatment of high-level wastes from the IFR fuel cycle

    SciTech Connect (OSTI)

    Johnson, T.R.; Lewis, M.A.; Newman, A.E.; Laidler, J.J.

    1992-01-01T23:59:59.000Z

    The Integral Fast Reactor (IFR) is being developed as a future commercial power source that promises to have important advantages over present reactors, including improved resource conservation and waste management. The spent metal alloy fuels from an IFR will be processed in an electrochemical cell operating at 500{degree}C with a molten chloride salt electrolyte and cadmium metal anode. After the actinides have been recovered from several batches of core and blanket fuels, the salt cadmium in this electrorefiner will be treated to separate fission products from residual transuranic elements. This treatment produces a waste salt that contains the alkali metal, alkaline earth, and halide fission products; some of the rare earths; and less than 100 nCi/g of alpha activity. The treated metal wastes contain the rest of the fission products (except T, Kr, and Xe) small amounts of uranium, and only trace amounts of transuranic elements. The current concept for the salt waste form is an aluminosilicate matrix, and the concept for the metal waste form is a corrosion-resistant metal alloy. The processes and equipment being developed to treat and immobilize the salt and metal wastes are described.

  15. Treatment of high-level wastes from the IFR fuel cycle

    SciTech Connect (OSTI)

    Johnson, T.R.; Lewis, M.A.; Newman, A.E.; Laidler, J.J.

    1992-08-01T23:59:59.000Z

    The Integral Fast Reactor (IFR) is being developed as a future commercial power source that promises to have important advantages over present reactors, including improved resource conservation and waste management. The spent metal alloy fuels from an IFR will be processed in an electrochemical cell operating at 500{degree}C with a molten chloride salt electrolyte and cadmium metal anode. After the actinides have been recovered from several batches of core and blanket fuels, the salt cadmium in this electrorefiner will be treated to separate fission products from residual transuranic elements. This treatment produces a waste salt that contains the alkali metal, alkaline earth, and halide fission products; some of the rare earths; and less than 100 nCi/g of alpha activity. The treated metal wastes contain the rest of the fission products (except T, Kr, and Xe) small amounts of uranium, and only trace amounts of transuranic elements. The current concept for the salt waste form is an aluminosilicate matrix, and the concept for the metal waste form is a corrosion-resistant metal alloy. The processes and equipment being developed to treat and immobilize the salt and metal wastes are described.

  16. EIS-0081: Long-Term Management of Liquid High-Level Radioactive Waste Stored at Western New York Nuclear Service Center, West Valley, New York

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy Office of Terminal Waste Disposal and Remedial Action prepared this environmental impact statement to analyze the environmental and socioeconomic impacts resulting from the Department’s proposed action to construct and operate facilities necessary to solidify the liquid high-level wastes currently stored in underground tanks at West Valley, New York.

  17. US Department of Energy interim mixed waste inventory report: Waste streams, treatment capacities and technologies: Volume 4, Site specific---Ohio through South Carolina

    SciTech Connect (OSTI)

    Not Available

    1993-04-01T23:59:59.000Z

    The Department of Energy (DOE) has prepared this report to provide an inventory of its mixed wastes and treatment capacities and technologies in response to Section 105(a) of the Federal Facility Compliance Act (FFCAct) of 1992 (Pub. L. No. 102-386). As required by the FFCAct-1992, this report provides site-specific information on DOE`s mixed waste streams and a general review of available and planned treatment facilities for mixed wastes at the following five Ohio facilities: Battelle Columbus Laboratories; Fernald Environmental Management Project; Mound Plant; Portsmouth Gaseous Diffusion Plant; and RMI, Titanium Company.

  18. Remediation of oil field wastes

    SciTech Connect (OSTI)

    Peters, R.W.; Wentz, C.A.

    1990-01-01T23:59:59.000Z

    Treatment and disposal of drilling muds and hazardous wastes has become a growing concern in the oil and gas industry. Further, past practices involving improper disposal require considerable research and cost to effectively remediate contaminated soils. This paper investigates two case histories describing the treatments employed to handle the liquid wastes involved. Both case histories describe the environmentally safe cleanup operations that were employed. 1 ref., 1 fig., 3 tabs.

  19. Feed Composition for Sodium-Bearing Waste Treatment Process, Rev. 3

    SciTech Connect (OSTI)

    Barnes, Charles Marshall

    2003-09-01T23:59:59.000Z

    Treatment of sodium-bearing waste (SBW) at the Idaho Nuclear Technology and Engineering Center (INTEC) within the Idaho National Engineering and Environmental Laboratory is mandated by a Settlement Agreement between the Department of Energy and the State of Idaho. One of the requirements of the Settlement Agreement is to complete treatment of SBW by December 31, 2012. To support both design and development studies for the SBW treatment process, detailed feed compositions are needed. This report contains the expected compositions of these feed streams and the sources and methods used in obtaining these compositions.

  20. Operating cost guidelines for benchmarking DOE thermal treatment systems for low-level mixed waste

    SciTech Connect (OSTI)

    Salmon, R.; Loghry, S.L.; Hermes, W.H.

    1994-11-01T23:59:59.000Z

    This report presents guidelines for estimating operating costs for use in benchmarking US Department of Energy (DOE) low-level mixed waste thermal treatment systems. The guidelines are based on operating cost experience at the DOE Toxic Substances Control Act (TSCA) mixed waste incinerator at the K-25 Site at Oak Ridge. In presenting these guidelines, it should be made clear at the outset that it is not the intention of this report to present operating cost estimates for new technologies, but only guidelines for estimating such costs.

  1. Waste Treatment & Immobilization Plant Project - Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of ScienceandMesa del SolStrengthening aTurbulenceUtilizeRural PublicRatesAbout Us > HanfordTreatment

  2. Independent Oversight Review, Hanford Site Waste Treatment and

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page onYouTube YouTube Note: Since the.pdfBreaking of BlytheDepartment of EnergyTreatment and Immobilization| Department

  3. Methods of producing alkylated hydrocarbons from an in situ heat treatment process liquid

    DOE Patents [OSTI]

    Roes, Augustinus Wilhelmus Maria (Houston, TX); Mo, Weijian (Sugar Land, TX); Muylle, Michel Serge Marie (Houston, TX); Mandema, Remco Hugo (Houston, TX); Nair, Vijay (Katy, TX)

    2009-09-01T23:59:59.000Z

    A method for producing alkylated hydrocarbons is disclosed. Formation fluid is produced from a subsurface in situ heat treatment process. The formation fluid is separated to produce a liquid stream and a first gas stream. The first gas stream includes olefins. The liquid stream is fractionated to produce at least a second gas stream including hydrocarbons having a carbon number of at least 3. The first gas stream and the second gas stream are introduced into an alkylation unit to produce alkylated hydrocarbons. At least a portion of the olefins in the first gas stream enhance alkylation.

  4. Integrated municipal solid waste treatment using a grate furnace incinerator: The Indaver case

    SciTech Connect (OSTI)

    Vandecasteele, C. [Department of Chemical Engineering, Katholieke Universiteit Leuven, De Croylaan 46, 3001 Leuven (Belgium)], E-mail: carlo.vandecasteele@cit.kuleuven.be; Wauters, G. [Indaver, Dijle 17a, 2800 Mechelen (Belgium); Arickx, S. [Department of Chemical Engineering, Katholieke Universiteit Leuven, De Croylaan 46, 3001 Leuven (Belgium); Jaspers, M. [Indaver, Dijle 17a, 2800 Mechelen (Belgium); Van Gerven, T. [Department of Chemical Engineering, Katholieke Universiteit Leuven, De Croylaan 46, 3001 Leuven (Belgium)

    2007-07-01T23:59:59.000Z

    An integrated installation for treatment of municipal solid waste and comparable waste from industrial origin is described. It consists of three grate furnace lines with flue gas treatment by half-wet scrubbing followed by wet scrubbing, and an installation for wet treatment of bottom ash. It is demonstrated that this integrated installation combines high recovery of energy (40.8% net) with high materials recovery. The following fractions were obtained after wet treatment of the bottom ash: ferrous metals, non-ferrous metals, three granulate fractions with different particle sizes, and sludge. The ferrous and non-ferrous metal fractions can both be recycled as high quality raw materials; the two larger particle size particle fractions can be applied as secondary raw materials in building applications; the sand fraction can be used for applications on a landfill; and the sludge is landfilled. For all components of interest, emissions to air are below the limit values. The integrated grate furnace installation is characterised by zero wastewater discharge and high occupational safety. Moreover, with the considered installation, major pollutants, such as PCDD/PCDF, Hg and iodine-136 are to a large extent removed from the environment and concentrated in a small residual waste stream (flue gas cleaning residue), which can be landfilled after stabilisation.

  5. PERFORMANCE IMPROVEMENT OF CROSS-FLOW FILTRATION FOR HIGH LEVEL WASTE TREATMENT

    SciTech Connect (OSTI)

    Duignan, M.; Nash, C.; Poirier, M.

    2011-01-12T23:59:59.000Z

    In the interest of accelerating waste treatment processing, the DOE has funded studies to better understand filtration with the goal of improving filter fluxes in existing cross-flow equipment. The Savannah River National Laboratory (SRNL) was included in those studies, with a focus on start-up techniques, filter cake development, the application of filter aids (cake forming solid precoats), and body feeds (flux enhancing polymers). This paper discusses the progress of those filter studies. Cross-flow filtration is a key process step in many operating and planned waste treatment facilities to separate undissolved solids from supernate slurries. This separation technology generally has the advantage of self-cleaning through the action of wall shear stress created by the flow of waste slurry through the filter tubes. However, the ability of filter wall self-cleaning depends on the slurry being filtered. Many of the alkaline radioactive wastes are extremely challenging to filtration, e.g., those containing compounds of aluminum and iron, which have particles whose size and morphology reduce permeability. Unfortunately, low filter flux can be a bottleneck in waste processing facilities such as the Savannah River Modular Caustic Side Solvent Extraction Unit and the Hanford Waste Treatment Plant. Any improvement to the filtration rate would lead directly to increased throughput of the entire process. To date increased rates are generally realized by either increasing the cross-flow filter axial flowrate, limited by pump capacity, or by increasing filter surface area, limited by space and increasing the required pump load. SRNL set up both dead-end and cross-flow filter tests to better understand filter performance based on filter media structure, flow conditions, filter cleaning, and several different types of filter aids and body feeds. Using non-radioactive simulated wastes, both chemically and physically similar to the actual radioactive wastes, the authors performed several tests to demonstrate increases in filter performance. With the proper use of filter flow conditions and filter enhancers, filter flow rates can be increased over rates currently realized today.

  6. Nuclear Waste Treatment Program annual report for FY 1988

    SciTech Connect (OSTI)

    Brouns, R.A.; Powell, J.A. (comps.)

    1989-11-01T23:59:59.000Z

    Much emphasis continues to be on the transfer of remote design technology for components integral to the West Valley Demonstration Project's (WVDP) vitrification process. In addition to preparing equipment specifications and drawings, Pacific Northwest Laboratory (PNL) staff also participated in numerous design coordination meetings and reviews of drawings prepared by other WVDP contractors. Nearly 200 jumper drawings for the vitrification cell were prepared by this program in FY 1988. The remote jumpers connect vessels in the cell to each other for the transfer of solutions and provide for the flow of materials, instrumentation signals, and power from outside the cell. Analysis required in preparing the jumper designs involved balance, thermal stress, seismic, set-down stress, and displacement calculations. Design efforts were begun on the canister decontamination and swipe station and on the remote maintenance station. Equipment selection and layouts of the vitrification off-gas treatment system, including a reamer to remotely clean the melter off-gas line, were finalized. Also finalized were the designs for the high-efficiency particulate air (HEPA) filter assemblies for heating, cooling and air conditioning of the vitrification cell.

  7. SCALE UP OF CERAMIC WASTE FORMS FOR THE EBR-II SPENT FUEL TREATMENT PROCESS

    SciTech Connect (OSTI)

    Matthew C. Morrison; Kenneth J. Bateman; Michael F. Simpson

    2010-11-01T23:59:59.000Z

    ABSTRACT SCALE UP OF CERAMIC WASTE FORMS FOR THE EBR-II SPENT FUEL TREATMENT PROCESS Matthew C. Morrison, Kenneth J. Bateman, Michael F. Simpson Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 The ceramic waste process is the intended method for disposing of waste salt electrolyte, which contains fission products from the fuel-processing electrorefiners (ER) at the INL. When mixed and processed with other materials, the waste salt can be stored in a durable ceramic waste form (CWF). The development of the CWF has recently progressed from small-scale testing and characterization to full-scale implementation and experimentation using surrogate materials in lieu of the ER electrolyte. Two full-scale (378 kg and 383 kg) CWF test runs have been successfully completed with final densities of 2.2 g/cm3 and 2.1 g/cm3, respectively. The purpose of the first CWF was to establish material preparation parameters. The emphasis of the second pre-qualification test run was to evaluate a preliminary multi-section CWF container design. Other considerations were to finalize material preparation parameters, measure the material height as it consolidates in the furnace, and identify when cracking occurs during the CWF cooldown process.

  8. Greater-Than-Class C low-level radioactive waste treatment technology evaluation

    SciTech Connect (OSTI)

    Garrison, T W; Fischer, D K

    1993-01-01T23:59:59.000Z

    This report was developed to provide the Greater-Than-Class C Low-Level Radioactive Waste Management Program with criteria and a methodology to select candidate treatment technologies for Greater-Than-Class C low-level radioactive waste (GTCC LLW) destined for dedicated storage and ultimately disposal. The technology selection criteria are provided in a Lotus spreadsheet format to allow the methodology to evolve as the GTCC LLW Program evolves. It is recognized that the final disposal facility is not yet defined; thus, the waste acceptance criteria and other facility-specific features are subject to change. The spreadsheet format will allow for these changes a they occur. As additional treatment information becomes available, it can be factored into the analysis. The technology selection criteria were established from program goals, draft waste acceptance criteria for dedicated storage (including applicable regulations), and accepted remedial investigation methods utilized under the Comprehensive Environmental Response, Compensation, and Liability Act. Kepner-Tregoe decisionmaking techniques are used to compare and rank technologies against the criteria.

  9. Recent Improvements In Interface Management For Hanfords Waste Treatment And Immobilization Plant - 13263

    SciTech Connect (OSTI)

    Arm, Stuart T. [Washington River Protection Solutions, Richland, WA (United States); Pell, Michael J. [Bechtel National, Inc., Richland, WA (United States); Van Meighem, Jeffery S. [Washington River Protection Solutions, Richland, WA (United States); Duncan, Garth M. [Bechtel National, Inc., Richland, WA (United States); Harrington, Christopher C. [Department of Energy, Office of River Protection, Richland, Washington (United States)

    2012-11-20T23:59:59.000Z

    The U.S. Department of Energy (DOE), Office of River Protection (ORP) is responsible for management and completion of the River Protection Project (RPP) mission, which comprises both the Hanford Site tank farms operations and the Waste Treatment and Immobilization Plant (WTP). The RPP mission is to store, retrieve and treat Hanford's tank waste; store and dispose of treated wastes; and close the tank farm waste management areas and treatment facilities by 2047. The WTP is currently being designed and constructed by Bechtel National Inc. (BNI) for DOE-ORP. BNI relies on a number oftechnical services from other Hanford contractors for WTP's construction and commissioning. These same services will be required of the future WTP operations contractor. The WTP interface management process has recently been improved through changes in organization and technical issue management documented in an Interface Management Plan. Ten of the thirteen active WTP Interface Control Documents (ICDs) have been revised in 2012 using the improved process with the remaining three in progress. The value of the process improvements is reflected by the ability to issue these documents on schedule.

  10. Development of the fluidized bed thermal treatment process for treating mixed waste

    SciTech Connect (OSTI)

    Semones, G.B.; Williams, P.M.; Stiefvater, S.P.; Mitchell, D.L.; Roecker, B.D.

    1993-05-01T23:59:59.000Z

    A fluidized bed system is being developed at Rocky Flats for the treatment of mixed waste (a mixture of radioactive and chemically hazardous waste). The current program builds on experience gained in the 1970`s and 1980`s in tests with bench-scale, pilot-scale, and demonstration-scale fluidized bed systems. The system operates at low temperatures ({approx} 525--600{degree}C) which eliminates many of the disadvantages associated with high temperature thermal treatment processes. The process has shown the ability to destroy polychlorinated biphenyls (PCB`s) with 99.9999% (``six-nines``) destruction efficiency in tests monitored by the Environmental Protection Agency (EPA). The bed makes use of in situ neutralization of acidic off-gases by incorporating sodium carbonate (Na{sub 2}CO{sub 3}) in the bed media. This eliminates using wet scrubbers to treat the off-gas; these produce a high volume of secondary waste. Once in operation, it is expected that the fluidized bed process will yield up to a 40:1 reduction in the volume of the waste.

  11. SUCCESSES AND EMERGING ISSUES IN SIMULATING THE MIXING BEHAVIOR OF LIQUID-PARTICLE NUCLEAR WASTE SLURRIES AT THE SAVANNAH RIVER SITE - 211B

    SciTech Connect (OSTI)

    Koopman, D.; Pickenheim, B.; Lambert, D.; Stone, M.

    2009-09-02T23:59:59.000Z

    Aqueous radioactive high-level waste slurries are combined during processing steps that ultimately produce a stable borosilicate glass waste form. Chemically treated waste slurries are combined with each other and with glass frit-water slurries to produce the melter feed. Understanding the evolution of the rheological properties of the slurries is an important aspect of removing and treating the stored waste. To a first approximation, combinations of colloidal waste slurry with {approx}0.1-mm mean diameter glass frit or glass beads act in an analogous matter to slurries of spherical beads in Newtonian liquids. The non-Newtonian rheological properties of the waste slurries without frit, however, add complexity to the hydrodynamic analysis. The use of shear rate dependent apparent viscosities with the modified Einstein equation was used to model the rheological properties of aqueous frit-waste slurries.

  12. Energy implications of mechanical and mechanical–biological treatment compared to direct waste-to-energy

    SciTech Connect (OSTI)

    Cimpan, Ciprian, E-mail: cic@kbm.sdu.dk; Wenzel, Henrik

    2013-07-15T23:59:59.000Z

    Highlights: • Compared systems achieve primary energy savings between 34 and 140 MJ{sub primary}/100 MJ{sub input} {sub waste.} • Savings magnitude is foremost determined by chosen primary energy and materials production. • Energy consumption and process losses can be upset by increased technology efficiency. • Material recovery accounts for significant shares of primary energy savings. • Direct waste-to-energy is highly efficient if cogeneration (CHP) is possible. - Abstract: Primary energy savings potential is used to compare five residual municipal solid waste treatment systems, including configurations with mechanical (MT) and mechanical–biological (MBT) pre-treatment, which produce waste-derived fuels (RDF and SRF), biogas and/or recover additional materials for recycling, alongside a system based on conventional mass burn waste-to-energy and ash treatment. To examine the magnitude of potential savings we consider two energy efficiency levels (state-of-the-art and best available technology), the inclusion/exclusion of heat recovery (CHP vs. PP) and three different background end-use energy production systems (coal condensing electricity and natural gas heat, Nordic electricity mix and natural gas heat, and coal CHP energy quality allocation). The systems achieved net primary energy savings in a range between 34 and 140 MJ{sub primary}/100 MJ{sub input} {sub waste}, in the different scenario settings. The energy footprint of transportation needs, pre-treatment and reprocessing of recyclable materials was 3–9.5%, 1–18% and 1–8% respectively, relative to total energy savings. Mass combustion WtE achieved the highest savings in scenarios with CHP production, nonetheless, MBT-based systems had similarly high performance if SRF streams were co-combusted with coal. When RDF and SRF was only used in dedicated WtE plants, MBT-based systems totalled lower savings due to inherent system losses and additional energy costs. In scenarios without heat recovery, the biodrying MBS-based system achieved the highest savings, on the condition of SRF co-combustion. As a sensitivity scenario, alternative utilisation of SRF in cement kilns was modelled. It supported similar or higher net savings for all pre-treatment systems compared to mass combustion WtE, except when WtE CHP was possible in the first two background energy scenarios. Recovery of plastics for recycling before energy recovery increased net energy savings in most scenario variations, over those of full stream combustion. Sensitivity to assumptions regarding virgin plastic substitution was tested and was found to mostly favour plastic recovery.

  13. Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

    SciTech Connect (OSTI)

    Neupauer, R.M.; Thurmond, S.M.

    1992-09-01T23:59:59.000Z

    This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

  14. Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory. Part 2, Chemical constituents

    SciTech Connect (OSTI)

    Neupauer, R.M.; Thurmond, S.M.

    1992-09-01T23:59:59.000Z

    This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

  15. Secondary Waste Form Development and Optimization—Cast Stone

    SciTech Connect (OSTI)

    Sundaram, S. K.; Parker, Kent E.; Valenta, Michelle M.; Pitman, Stan G.; Chun, Jaehun; Chung, Chul-Woo; Kimura, Marcia L.; Burns, Carolyn A.; Um, Wooyong; Westsik, Joseph H.

    2011-07-14T23:59:59.000Z

    Washington River Protection Services is considering the design and construction of a Solidification Treatment Unit (STU) for the Effluent Treatment Facility (ETF) at Hanford. The ETF is a Resource Conservation and Recovery Act-permitted, multi-waste, treatment and storage unit and can accept dangerous, low-level, and mixed wastewaters for treatment. The STU needs to be operational by 2018 to receive secondary liquid wastes generated during operation of the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The STU to ETF will provide the additional capacity needed for ETF to process the increased volume of secondary wastes expected to be produced by WTP.

  16. Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario hydro`s Bruce nuclear generating station {open_quotes}A{close_quotes}

    SciTech Connect (OSTI)

    Day, J.E.; Baker, R.L. [ADTECHS Corporation, Herndon, VA (United States)

    1994-12-31T23:59:59.000Z

    Ontario Hydro at the Bruce Nuclear Generating Station {open_quotes}A{close_quotes} has undertaken a program to render the station`s liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology.

  17. METHODS FOR DETERMINING AGITATOR MIXING REQUIREMENTS FOR A MIXING & SAMPLING FACILITY TO FEED WTP (WASTE TREATMENT PLANT)

    SciTech Connect (OSTI)

    GRIFFIN PW

    2009-08-27T23:59:59.000Z

    The following report is a summary of work conducted to evaluate the ability of existing correlative techniques and alternative methods to accurately estimate impeller speed and power requirements for mechanical mixers proposed for use in a mixing and sampling facility (MSF). The proposed facility would accept high level waste sludges from Hanford double-shell tanks and feed uniformly mixed high level waste to the Waste Treatment Plant. Numerous methods are evaluated and discussed, and resulting recommendations provided.

  18. Quantification and Physics of Cold Plasma Treatment of Organic Liquid Surfaces

    E-Print Network [OSTI]

    Edward Bormashenko; Victor Multanen; Gilad Chaniel; Roman Grynyov; Evgeny Shulzinger; Roman Pogreb; Hadas Aharoni; Yakir Nagar

    2015-03-02T23:59:59.000Z

    Plasma treatment increases the surface energy of condensed phases: solids and liquids. Two independent methods of the quantification of the influence imposed by a cold radiofrequency air plasma treatment on the surface properties of silicone oils (polydimethylsiloxane) of various molecular masses and castor oil are introduced. Under the first method the water droplet coated by oils was exposed to the cold air radiofrequency plasma, resulting in an increase of oil/air surface energy. An expression relating the oil/air surface energy to the apparent contact angle of the water droplet coated with oil was derived. The apparent contact angle was established experimentally. Calculation of the oil/air surface energy and spreading parameter was carried out for the various plasma-treated silicone and castor oils. The second method is based on the measurement of the electret response of the plasma-treated liquids.

  19. Hanford Waste Treatment Plant places first complex piping module in Pretreatment Facility

    Broader source: Energy.gov [DOE]

    Crews at the Hanford Waste Treatment Plant, also known as the "Vit Plant," placed a 19-ton piping module inside the Pretreatment Facility. The module was lifted over 98-foot-tall walls and lowered into a space that provided less than two inches of clearance on each side and just a few feet on each end. It was set 56 feet above the ground.

  20. Operational experience of the Juelich incineration system in the treatment of radioactive waste

    SciTech Connect (OSTI)

    Halaszovich, S.; Jablonski, W. [Forschungszentrum Juelich (Germany); Lins, W.; Wurster, W.; Kaufmann, K.H. [Kraftanlagen Aktiengesellschaft, Heidelberg (Germany)

    1993-12-31T23:59:59.000Z

    After ten years spent on development and testing of a prototype incinerator in the Juelich Research Center, a new industrial scale unit has been built. The paper gives a short description of the plant design and operation characteristics. The major part of the paper deals with the experience gained from the treatment of 355 Mg low-level radioactive waste during the last four years.

  1. Low-level waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the US Department of Energy waste management programmatic environmental impact statement

    SciTech Connect (OSTI)

    Goyette, M.L.; Dolak, D.A.

    1996-12-01T23:59:59.000Z

    This report provides technical support information for use in analyzing environmental impacts associated with U.S. Department of Energy (DOE) low-level radioactive waste (LLW) management alternatives in the Waste-Management (WM) Programmatic Environmental Impact Statement (PEIS). Waste loads treated and disposed of for each of the LLW alternatives considered in the DOE WM PEIS are presented. Waste loads are presented for DOE Waste Management (WM) wastes, which are generated from routine operations. Radioactivity concentrations and waste quantities for treatment and disposal under the different LLW alternatives are described for WM waste. 76 refs., 14 figs., 42 tabs.

  2. The Polymers for Liquid Radioactive Waste Solidification: a Lost Chapter in the History of Engineering or a Step Forward? - 13529

    SciTech Connect (OSTI)

    Pokhitonov, Yury [V.G. Khlopin Radium Institute, St. Petersburg (Russian Federation)] [V.G. Khlopin Radium Institute, St. Petersburg (Russian Federation); Kelley, Dennis [Pacific Nuclear Solutions, Indianapolis, Indiana (United States)] [Pacific Nuclear Solutions, Indianapolis, Indiana (United States)

    2013-07-01T23:59:59.000Z

    Ideas on the application of polymers for the liquid radioactive waste immobilization go a way back, and the first studies in the area were published 30-40 years ago. One should admit that regardless of the fairly large number of publications appeared in the past years currently the interest in this work came down greatly. It was the successful assimilation and worldwide implementation of the LRW cementation technology caused a slump in the interest in polymers. But today it's safe to say that the situation slowly changes, particularly due to the market appearance of the high-tech polymers manufactured by Nochar Company, and unique properties of these polymers gradually raise the demand in various countries. The results of multiple experiments performed with the simulated solutions have passed the comprehensive tests with actual waste. The economic effect from the implementation of the new technology is defined by the volume reduction of waste coming onto the repository, by the decline in the cost of transportation and of the repository construction on account of cutting down the construction volume. Interesting results have been obtained during the search for the technical decisions that would allow using the polymer materials in the processing technology of the industrial toxic waste. One more promising area of the possible application of polymers should be pointed out. It is the application of polymer materials as the assets for the emergency damage control when the advantages of the polymers become obvious. (authors)

  3. Risk assessment of CST-7 proposed waste treatment and storage facilities Volume I: Limited-scope probabilistic risk assessment (PRA) of proposed CST-7 waste treatment & storage facilities. Volume II: Preliminary hazards analysis of proposed CST-7 waste storage & treatment facilities

    SciTech Connect (OSTI)

    Sasser, K.

    1994-06-01T23:59:59.000Z

    In FY 1993, the Los Alamos National Laboratory Waste Management Group [CST-7 (formerly EM-7)] requested the Probabilistic Risk and Hazards Analysis Group [TSA-11 (formerly N-6)] to conduct a study of the hazards associated with several CST-7 facilities. Among these facilities are the Hazardous Waste Treatment Facility (HWTF), the HWTF Drum Storage Building (DSB), and the Mixed Waste Receiving and Storage Facility (MWRSF), which are proposed for construction beginning in 1996. These facilities are needed to upgrade the Laboratory`s storage capability for hazardous and mixed wastes and to provide treatment capabilities for wastes in cases where offsite treatment is not available or desirable. These facilities will assist Los Alamos in complying with federal and state requlations.

  4. A delayed-neutron monitor for a liquid-waste stream with high gamma-ray intensity

    SciTech Connect (OSTI)

    Rinard, P.M.; Crane, T.W.; Van Lyssel, T.; Kroncke, K.M.; Schneider, C.M.; Bourret, S.C. (Los Alamos National Lab., NM (USA))

    1989-01-01T23:59:59.000Z

    An instrument has been built to monitor the uranium concentration in a liquid-waste stream to avoid a criticality accident in a downstream holding tank. The measurement technique is based on the production and counting of delayed neutrons using the shuffler'' process because the waste contains enough fission products to produce a gamma-ray dose rate of 10 R/h on the surface of the assay tank. The design goal was a sensitivity of 0.034 g/L (1{sigma} = 10%) in 100 s as the stream flows at 80 L/h through the assay chamber. The instrument is to run unattended for at least three months; during this time it it to transmit assay results to the plant computer and generate warnings and alarms when necessary.

  5. ENVIROCARE OF UTAH: EXPANDING WASTE ACCEPTANCE CRITERIA TO PROVIDE LOW-LEVEL AND MIXED WASTE DISPOSAL OPTIONS

    SciTech Connect (OSTI)

    Rogers, B.; Loveland, K.

    2003-02-27T23:59:59.000Z

    Envirocare of Utah operates a low-level radioactive waste disposal facility 80 miles west of Salt Lake City in Clive, Utah. Accepted waste types includes NORM, 11e2 byproduct material, Class A low-level waste, and mixed waste. Since 1988, Envirocare has offered disposal options for environmental restoration waste for both government and commercial remediation projects. Annual waste receipts exceed 12 million cubic feet. The waste acceptance criteria (WAC) for the Envirocare facility have significantly expanded to accommodate the changing needs of restoration projects and waste generators since its inception, including acceptable physical waste forms, radiological acceptance criteria, RCRA requirements and treatment capabilities, PCB acceptance, and liquids acceptance. Additionally, there are many packaging, transportation, and waste management options for waste streams acceptable at Envirocare. Many subcontracting vehicles are also available to waste generators for both government and commercial activities.

  6. Proposed Use of a Constructed Wetland for the Treatment of Metals in the S-04 Outfall of the Defense Waste Processing Facility at the Savannah River Site

    SciTech Connect (OSTI)

    Glover, T.

    1999-11-23T23:59:59.000Z

    The DWPF is part of an integrated waste treatment system at the SRS to treat wastes containing radioactive contaminants. In the early 1980s the DOE recognized that there would be significant safety and cost advantages associated with immobilizing the radioactive waste in a stable solid form. The Defense Waste Processing Facility was designed and constructed to accomplish this task.

  7. Phase 2 THOR Steam Reforming Tests for Sodium Bearing Waste Treatment

    SciTech Connect (OSTI)

    Nicholas R. Soelberg

    2004-01-01T23:59:59.000Z

    About one million gallons of acidic, hazardous, and radioactive sodium-bearing waste is stored in stainless steel tanks at the Idaho Nuclear Technology and Engineering Center (INTEC), which is a major operating facility of the Idaho National Engineering and Environmental Laboratory. Steam reforming is a candidate technology being investigated for converting the waste into a road ready waste form that can be shipped to the Waste Isolation Pilot Plant in New Mexico for interment. A steam reforming technology patented by Studsvik, Inc., and licensed to THOR Treatment Technologies has been tested in two phases using a Department of Energy-owned fluidized bed test system located at the Science Applications International Corporation (SAIC) Science and Technology Applications Research Center located in Idaho Falls, Idaho. The Phase 1 tests were reported earlier in 2003. The Phase 2 tests are reported here. For Phase 2, the process feed rate, stoichiometry, and chemistry were varied to identify and demonstrate process operation and product characteristics under different operating conditions. Two test series were performed. During the first series, the process chemistry was designed to produce a sodium carbonate product. The second series was designed to produce a more leach-resistant, mineralized sodium aluminosilicate product. The tests also demonstrated the performance of a MACT-compliant off-gas system.

  8. Characterization of Irradiated Metal Waste from the Pyrometallurgical Treatment of Used EBR-II Fuel

    SciTech Connect (OSTI)

    B.R. Westphal; K.C. Marsden; W.M. McCartin; S.M. Frank; D.D. Keiser, Jr.; T.S. Yoo; D. Vaden; D.G. Cummings; K.J. Bateman; J. J. Giglio; T. P. O'Holleran; P. A. Hahn; M. N. Patterson

    2013-03-01T23:59:59.000Z

    As part of the pyrometallurgical treatment of used Experimental Breeder Reactor-II fuel, a metal waste stream is generated consisting primarily of cladding hulls laden with fission products noble to the electrorefining process. Consolidation by melting at high temperature [1873 K (1600 degrees C)] has been developed to sequester the noble metal fission products (Zr, Mo, Tc, Ru, Rh, Te, and Pd) which remain in the iron-based cladding hulls. Zirconium from the uranium fuel alloy (U-10Zr) is also deposited on the hulls and forms Fe-Zr intermetallics which incorporate the noble metals as well as residual actinides during processing. Hence, Zr has been chosen as the primary indicator for consistency of the metal waste. Recently, the first production-scale metal waste ingot was generated and sampled to monitor Zr content for Fe-Zr intermetallic phase formation and validation of processing conditions. Chemical assay of the metal waste ingot revealed a homogeneous distribution of the noble metal fission products as well as the primary fuel constituents U and Zr. Microstructural characterization of the ingot confirmed the immobilization of the noble metals in the Fe-Zr intermetallic phase.

  9. Decontamination and inspection plan for Phase 3 closure of the 300 area waste acid treatment system

    SciTech Connect (OSTI)

    LUKE, S.N.

    1999-02-01T23:59:59.000Z

    This decontamination and inspection plan (DIP) describes decontamination and verification activities in support of Phase 3 closure of the 300 Area Waste Acid Treatment System (WATS). Phase 3 is the third phase of three WATS closure phases. Phase 3 attains clean closure conditions for WATS portions of the 334 and 311 Tank Farms (TF) and the 333 and 303-F Buildings. This DIP also describes designation and management of waste and debris generated during Phase 3 closure activities. Information regarding Phase 1 and Phase 2 for decontamination and verification activities closure can be found in WHC-SD-ENV-AP-001 and HNF-1784, respectively. This DIP is provided as a supplement to the closure plan (DOE/RL-90-11). This DIP provides the documentation for Ecology concurrence with Phase 3 closure methods and activities. This DIP is intended to provide greater detail than is contained in the closure plan to satisfy Ecology Dangerous Waste Regulations, Washington Administrative Code (WAC) 173-303-610 requirement that closure documents describe the methods for removing, transporting, storing, and disposing of all dangerous waste at the unit. The decontamination and verification activities described in this DIP are based on the closure plan and on agreements reached between Ecology and the U.S. Department of Energy, Richland Operations Office (DOE-RL) during Phase 3 closure activity workshops and/or project manager meetings (PMMs).

  10. Vitrification treatment options for disposal of greater-than-Class-C low-level waste in a deep geologic repository

    SciTech Connect (OSTI)

    Fullmer, K.S.; Fish, L.W.; Fischer, D.K.

    1994-11-01T23:59:59.000Z

    The Department of Energy (DOE), in keeping with their responsibility under Public Law 99-240, the Low-Level Radioactive Waste Policy Amendments Act of 1985, is investigating several disposal options for greater-than-Class C low-level waste (GTCC LLW), including emplacement in a deep geologic repository. At the present time vitrification, namely borosilicate glass, is the standard waste form assumed for high-level waste accepted into the Civilian Radioactive Waste Management System. This report supports DOE`s investigation of the deep geologic disposal option by comparing the vitrification treatments that are able to convert those GTCC LLWs that are inherently migratory into stable waste forms acceptable for disposal in a deep geologic repository. Eight vitrification treatments that utilize glass, glass ceramic, or basalt waste form matrices are identified. Six of these are discussed in detail, stating the advantages and limitations of each relative to their ability to immobilize GTCC LLW. The report concludes that the waste form most likely to provide the best composite of performance characteristics for GTCC process waste is Iron Enriched Basalt 4 (IEB4).

  11. Advanced oxidation treatment of high strength bilge and aqueous petroleum waste

    SciTech Connect (OSTI)

    Hulsey, R.A.; Kobylinski, E.A. [Black and Veatch, Kansas City, MO (United States); Leach, B. [EEC, Inc., Virginia Beach, VA (United States); Pearce, L. [TRITECH, Greensboro, NC (United States)

    1996-11-01T23:59:59.000Z

    The Craney Island Fuel Depot is the largest US Navy fuel terminal in the continental US. Services provided at this facility include fuel storage (current capacity is 1.5 million barrels), fuel reclamation (recovery of oil from oily wastewater), and physical/chemical treatment for the removal of residual oil from bilge water and from aqueous petroleum waste. Current wastewater treatment consists of storage/equalization, oil/water separation, dissolved air flotation, sand filtration, and carbon adsorption. The Navy initiated this study to comply with the State requirement that its existing physical/chemical oily wastewater treatment plant be upgraded to remove soluble organics and produce an effluent which would meet acute toxicity limits. The pilot tests conducted during the study included several variations of chemical and biological wastewater treatment processes. While biological treatment alone was capable of meeting the proposed BOD limit of 26 mg/L, the study showed that the effluent of the biological process contained a high concentration of refractory (nonbiodegradable) organics and could not consistently meet the proposed limits for COD and TOC when treating high-strength wastewater. Additional tests were conducted with advanced oxidation processes (AOPs). AOPs were evaluated for use as independent treatment processes as well as polishing processes following biological treatment. The AOP processes used for this study included combinations of ozone (O{sub 3}) ultraviolet radiation (UV), and hydrogen peroxide (H{sub 2}O{sub 2}).

  12. Information related to low-level mixed waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement

    SciTech Connect (OSTI)

    Wilkins, B.D.; Dolak, D.A.; Wang, Y.Y.; Meshkov, N.K.

    1996-12-01T23:59:59.000Z

    This report was prepared to support the analysis of risks and costs associated with the proposed treatment of low-level mixed waste (LLMW) under management of the US Department of Energy (DOE). The various waste management alternatives for treatment of LLMW have been defined in the DOE`s Office of Waste Management Programmatic Environmental Impact Statement. This technical memorandum estimates the waste material throughput expected at each proposed LLMW treatment facility and analyzes potential radiological and chemical releases at each DOE site resulting from treatment of these wastes. Models have been developed to generate site-dependent radiological profiles and waste-stream-dependent chemical profiles for these wastes. Current site-dependent inventories and estimates for future generation of LLMW have been obtained from DOE`s 1994 Mixed Waste Inventory Report (MWIR-2). Using treatment procedures developed by the Mixed Waste Treatment Project, the MWIR-2 database was analyzed to provide waste throughput and emission estimates for each of the different waste types assessed in this report. Uncertainties in the estimates at each site are discussed for waste material throughputs and radiological and chemical releases.

  13. Testing and Disposal Strategy for Secondary Wastes from Vitrification of Sodium-Bearing Waste at Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    Herbst, Alan K.

    2002-01-02T23:59:59.000Z

    The Idaho National Engineering and Environmental Laboratory (INEEL) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates.

  14. Testing and Disposal Strategy for Secondary Wastes from Vitrification of Sodium-Bearing Waste at the Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    Herbst, Alan Keith

    2002-01-01T23:59:59.000Z

    The Idaho National Engineering and Environmental Laboratory (INEEL) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates.

  15. XRF and leaching characterization of waste glasses derived from wastewater treatment sludges

    SciTech Connect (OSTI)

    Ragsdale, R.G., Jr

    1994-12-01T23:59:59.000Z

    Purpose of this study was to investigate use of XRF (x-ray fluorescence spectrometry) as a near real-time method to determine melter glass compositions. A range of glasses derived from wastewater treatment sludges associated with DOE sites was prepared. They were analyzed by XRF and wet chemistry digestion with atomic absorption/inductively coupled emission spectrometry. Results indicated good correlation between these two methods. A rapid sample preparation and analysis technique was developed and demonstrated by acquiring a sample from a pilot-scale simulated waste glass melter and analyzing it by XRF within one hour. From the results, XRF shows excellent potential as a process control tool for waste glass vitrification. Glasses prepared for this study were further analyzed for durability by toxicity characteristic leaching procedure and product consistency test and results are presented.

  16. Solvated electron yields in liquid and supercritical ammonia-A statistical mechanical treatment

    SciTech Connect (OSTI)

    Schiller, Robert; Horvath, Akos [Centre for Energy Research, P.O.B. 49, Budapest H-1525 (Hungary)

    2012-12-07T23:59:59.000Z

    Earlier the geminate recombination of ions and solvated electrons, produced by ionizing radiation or laser light, was theoretically treated by a model which consisted of a Rydberg atom interacting with the thermodynamic fluctuations of the medium [R. Schiller, J. Chem. Phys. 92, 5527 (1990)]. The theory was applied to liquid-to-supercritical water [R. Schiller and A. Horvath, J. Chem. Phys. 135, 084510 (2011)]. Now it is compared with recent experiments performed on liquid-to-supercritical ammonia [J. Urbanek, A. Dahmen, J. Torres-Alacan, P. Koenigshoven, J. Lindner, and P. Voehringer, J. Phys. Chem. B 116, 2223 (2012)]. The agreement between theory and experiment seems to be reasonable. The treatment is critically assessed.

  17. Scaled Testing to Evaluate Pulse Jet Mixer Performance in Waste Treatment Plant Mixing Vessels

    SciTech Connect (OSTI)

    Fort, James A.; Meyer, Perry A.; Bamberger, Judith A.; Enderlin, Carl W.; Scott, Paul A.; Minette, Michael J.; Gauglitz, Phillip A.

    2010-03-07T23:59:59.000Z

    The Waste Treatment and Immobilization Plant (WTP) at Hanford is being designed and built to pre-treat and vitrify the waste in Hanford’s 177 underground waste storage tanks. Numerous process vessels will hold waste at various stages in the WTP. These vessels have pulse jet mixer (PJM) systems. A test program was developed to evaluate the adequacy of mixing system designs in the solids-containing vessels in the WTP. The program focused mainly on non-cohesive solids behavior. Specifically, the program addressed the effectiveness of the mixing systems to suspend settled solids off the vessel bottom, and distribute the solids vertically. Experiments were conducted at three scales using various particulate simulants. A range of solids loadings and operational parameters were evaluated, including jet velocity, pulse volume, and duty cycle. In place of actual PJMs, the tests used direct injection from tubes with suction at the top of the tank fluid. This gave better control over the discharge duration and duty cycle and simplified the facility requirements. The mixing system configurations represented in testing varied from 4 to 12 PJMs with various jet nozzle sizes. In this way the results collected could be applied to the broad range of WTP vessels with varying geometrical configurations and planned operating conditions. Data for “just-suspended velocity”, solids cloud height, and solids concentration vertical profile were collected, analyzed, and correlated. The correlations were successfully benchmarked against previous large-scale test results, then applied to the WTP vessels using reasonable assumptions of anticipated waste properties to evaluate adequacy of the existing mixing system designs.

  18. Identification of the source of methane at a hazardous waste treatment facility using isotopic analysis

    SciTech Connect (OSTI)

    Hackley, K.C.; Liu, C.L. (Illinois State Geological Survey, Peabody, IL (United States)); Trainor, D.P. (Dames and Moore, Madison, WI (United States))

    1992-01-01T23:59:59.000Z

    Isotopic analyses have been used to determine the source of methane in subsurface sediments at a hazardous waste treatment facility in the Lake Calumet area of Chicago, Illinois. The study area is surrounded by landfills and other waste management operations and has a long history of waste disposal. The facility property consists of land constructed of approximately 15 feet of fill placed over lake sediments. The fill is underlain by successively older lacustrine and glacial till deposits to a maximum depth of approximately 80 feet. During a subsurface investigation of the site performed for a RCRA Facility Investigation of former solid waste management units (SWMUs) in the fill, significant quantities of methane were encountered in the natural deposits. Gas samples were collected from the headspace of 11 piezometers screened at depths of approximately 30, 40, and 50 feet beneath the surface. Methane concentrations up to 75% by volume were observed in some of the piezometers. Stable isotope analyses were completed on methane and associated CO[sub 2] separated from the gas samples. Radiocarbon (C-14) analyses were also completed on several of the samples. The delta C-13 results for the intermediate and deep zones are indicative of methane produced by microbial reduction of CO[sub 2]. The methane occurring in the shallow zone appears to be a mixture of methane from the intermediate zone and methane produced by microbial fermentation of naturally (nonanthropogenic) buried organic matter within the shallow lacustrine sediments. According to the isotopic and chemical results, the methane does not appear to be related to gas generation from nearby landfills or from organic wastes previously placed in the former facility SWMUs.

  19. Waste Treatment Plant Support Program: Summaries of Reports Produced During Fiscal Years 1999-2010

    SciTech Connect (OSTI)

    Beeman, Gordon H.

    2010-08-12T23:59:59.000Z

    The Waste Treatment Plant (WTP) being built on the U.S. Department of Energy (DOE) Hanford Site will be the largest chemical processing plant in the United States. Bechtel National Inc. (BNI) is the designer and constructor for the WTP. The Pacific Northwest National Laboratory (PNNL) has provided significant research and testing support to the WTP. This report provides a summary of reports developed initially under PNNL’s “1831” use agreement and later PNNL’s “1830” prime contract with DOE in support of the WTP. In March 2001, PNNL under its “1831” use agreement entered into a contract with BNI to support their research and testing activities. However, PNNL support to the WTP predates BNI involvement. Prior to March 2001, PNNL supported British Nuclear Fuels Ltd. in its role as overall designer and constructor. In February 2007, execution of PNNL’s support to the WTP was moved under its “1830” prime contract with DOE. Documents numbered “PNWD-XXXX” were issued under PNNL’s “1831” use agreement. Documents numbered “PNNL-XXXX” were issued under PNNL’s “1830” prime contract with DOE. The documents are sorted by fiscal year and categorized as follows: ? Characterization ? HLW (High Level Waste) ? Material Characterization ? Pretreatment ? Simulant Development ? Vitrification ? Waste Form Qualification. This report is intended to provide a compendium of reports issued by PNWD/PNNL in support of the Waste Treatment Plant. Copies of all reports can be obtained by clicking on http://www.pnl.gov/rpp-wtp/ and downloading the .pdf file(s) to your computer.

  20. Recent Improvements in Interface Management for Hanford's Waste Treatment and Immobilization Plant - 13263

    SciTech Connect (OSTI)

    Arm, Stuart T.; Van Meighem, Jeffery S. [Washington River Protection Solutions, P.O. Box 850, Richland, Washington, 99352 (United States)] [Washington River Protection Solutions, P.O. Box 850, Richland, Washington, 99352 (United States); Duncan, Garth M.; Pell, Michael J. [Bechtel National Inc., 2435 Stevens Center Place, Richland, Washington, 99352 (United States)] [Bechtel National Inc., 2435 Stevens Center Place, Richland, Washington, 99352 (United States); Harrington, Christopher C. [Department of Energy - Office of River Protection, 2440 Stevens Center Place, Richland, Washington, 99352 (United States)] [Department of Energy - Office of River Protection, 2440 Stevens Center Place, Richland, Washington, 99352 (United States)

    2013-07-01T23:59:59.000Z

    The U.S. Department of Energy (DOE), Office of River Protection (ORP) is responsible for management and completion of the River Protection Project (RPP) mission, which includes the Hanford Site tank farms operations and the Waste Treatment and Immobilization Plant (WTP). The RPP mission is to store, retrieve and treat Hanford's tank waste; store and dispose of treated wastes; and close the tank farm waste management areas and treatment facilities by 2047. The WTP is currently being designed and constructed by Bechtel National Inc. (BNI) for DOE-ORP. BNI relies on a number of technical services from other Hanford contractors for WTP's construction and commissioning. These same services will be required of the future WTP operations contractor. Partly in response to a DNFSB recommendation, the WTP interface management process managing these technical services has recently been improved through changes in organization and issue management. The changes are documented in an Interface Management Plan. The organizational improvement is embodied in the One System Integrated Project Team that was formed by integrating WTP and tank farms staff representing interfacing functional areas into a single organization. A number of improvements were made to the issue management process but most notable was the formal appointment of technical, regulatory and safety subject matter experts to ensure accurate identification of issues and open items. Ten of the thirteen active WTP Interface Control Documents have been revised in 2012 using the improved process with the remaining three in progress. The value of the process improvements is reflected by the ability to issue these documents on schedule and accurately identify technical, regulatory and safety issues and open items. (authors)

  1. Separation and Purification and Beta Liquid Scintillation Analysis of Sm-151 in Savannah River Site and Hanford Site DOE High Level Waste

    SciTech Connect (OSTI)

    Dewberry, R.A.

    2001-02-13T23:59:59.000Z

    This paper describes development work to obtain a product phase of Sm-151 pure of any other radioactive species so that it can be determined in US Department of Energy high level liquid waste and low level solid waste by liquid scintillation {beta}-spectroscopy. The technique provides separation from {mu}Ci/ml levels of Cs-137, Pu alpha and Pu-241 {beta}-decay activity, and Sr-90/Y-90 activity. The separation technique is also demonstrated to be useful for the determination of Pm-147.

  2. Feasibility study for thermal treatment of solid tire wastes in Bangladesh by using pyrolysis technology

    SciTech Connect (OSTI)

    Islam, M.R., E-mail: mrislam1985@yahoo.com [Department of Mechanical Engineering, Rajshahi University of Engineering and Technology, Rajshahi 6204 (Bangladesh); Joardder, M.U.H.; Hasan, S.M. [Department of Mechanical Engineering, Rajshahi University of Engineering and Technology, Rajshahi 6204 (Bangladesh); Takai, K.; Haniu, H. [Department of Mechanical Engineering, National University Corporation Kitami Institute of Technology, 165 Koen-cho, Kitami City, Hokkaido 090-8507 (Japan)

    2011-09-15T23:59:59.000Z

    In this study on the basis of lab data and available resources in Bangladesh, feasibility study has been carried out for pyrolysis process converting solid tire wastes into pyrolysis oils, solid char and gases. The process considered for detailed analysis was fixed-bed fire-tube heating pyrolysis reactor system. The comparative techno-economic assessment was carried out in US$ for three different sizes plants: medium commercial scale (144 tons/day), small commercial scale (36 tons/day), pilot scale (3.6 tons/day). The assessment showed that medium commercial scale plant was economically feasible, with the lowest unit production cost than small commercial and pilot scale plants for the production of crude pyrolysis oil that could be used as boiler fuel oil and for the production of upgraded liquid-products.

  3. Engineering assessment of low-level liquid waste disposal caisson locations at the 618-11 Burial Grounds

    SciTech Connect (OSTI)

    Phillips, S.J.; Fischer, D.D.; Crawford, R.C. [Westinghouse Hanford Co., Richland, WA (United States); Rising, J.L. [Pacific Northwest Lab., Richland, WA (United States)

    1982-06-01T23:59:59.000Z

    Rockwell Hanford Operations is currently involved in an extensive effort to perform interim ground surface stabilization activities at retired low-level waste burial grounds located at the Hanford Site, Richland, Washington. The principal objective of these activities is to promote increased occupational and radiological safety at burial grounds. Interim stabilization activities include: (1) load testing (traversing burial ground surfaces with heavy equipment to promote incipient collapse of void spaces within the disposal structure and overburden), (2) barrier placement (placement of a {ge} 0.6 m soil barrier over existing overburden), and (3) revegetation (establishment of shallow rooted vegetation on the barrier to mitigate deep rooted plant growth and to reduce erosion). Low-level waste disposal caissons were used in 300 Area Burial Grounds as internment structures for containerized liquid wastes. These caissons, by virtue of their contents, design and methods of closure, require long-term performance evaluation. As an initial activity to evaluate long-term performance, the accurate location of these structures is required. This topical report summarizes engineering activities used to locate caissons in the subsurface environment at the Burial Ground. Activities were conducted to locate caissons during surface stabilization activities. The surface locations were marked, photographed, and recorded on an as built engineering drawing. The recorded location of these caissons will augment long-term observations of confinement structure and engineered surface barrier performance. In addition, accurate caisson location will minimize occupational risk during monitoring and observation activities periodically conducted at the burial ground.

  4. Waste Generated from LMR-AMTEC Reactor Concept

    SciTech Connect (OSTI)

    Hasan, Ahmed; Mohamed, Yasser, T.; Mohammaden, Tarek, F.

    2003-02-25T23:59:59.000Z

    The candidate Liquid Metal Reactor-Alkali Metal Thermal -to- Electric Converter (LMR-AMTEC) is considered to be the first reactor that would use pure liquid potassium as a secondary coolant, in which potassium vapor aids in the conversion of thermal energy to electric energy. As with all energy production, the thermal generation of electricity produces wastes. These wastes must be managed in ways which safeguard human health and minimize their impact on the environment. Nuclear power is the only energy industry, which takes full responsibility for all its wastes. Based on the candidate design of the LMR-AMTEC components and the coolant types, different wastes will be generated from LMR. These wastes must be classified and characterized according to the U.S. Code of Federal Regulation, CFR. This paper defines the waste generation and waste characterization from LMR-AMTEC and reviews the applicable U.S. regulations that govern waste transportation, treatment, storage and final disposition. The wastes generated from LMR-AMTEC are characterized as: (1) mixed waste which is generated from liquid sodium contaminated by fission products and activated corrosion products; (2) hazardous waste which is generated from liquid potassium contaminated by corrosion products; (3) spent nuclear fuel; and (4) low-level radioactive waste which is generated from the packing materials (e.g. activated carbon in cold trap and purification units). The regulations and management of these wastes are summarized in this paper.

  5. Grand Junction projects office mixed-waste treatment program, VAC*TRAX mobile treatment unit process hazards analysis

    SciTech Connect (OSTI)

    Bloom, R.R.

    1996-04-01T23:59:59.000Z

    The objective of this report is to demonstrate that a thorough assessment of the risks associated with the operation of the Rust Geotech patented VAC*TRAX mobile treatment unit (MTU) has been performed and documented. The MTU was developed to treat mixed wastes at the US Department of Energy (DOE) Albuquerque Operations Office sites. The MTU uses an indirectly heated, batch vacuum dryer to thermally desorb organic compounds from mixed wastes. This process hazards analysis evaluated 102 potential hazards. The three significant hazards identified involved the inclusion of oxygen in a process that also included an ignition source and fuel. Changes to the design of the MTU were made concurrent with the hazard identification and analysis; all hazards with initial risk rankings of 1 or 2 were reduced to acceptable risk rankings of 3 or 4. The overall risk to any population group from operation of the MTU was determined to be very low; the MTU is classified as a Radiological Facility with low hazards.

  6. TREATMENT OF METAL-LADEN HAZARDOUS WASTES WITH ADVANCED CLEAN COAL TECHNOLOGY BY-PRODUCTS

    SciTech Connect (OSTI)

    James T. Cobb, Jr.; Ronald D. Neufeld; Jana Agostini

    1999-05-10T23:59:59.000Z

    This fourteenth quarterly report describes work done during the fourteenth three-month period of the University of Pittsburgh's project on the ''Treatment of Metal-Laden Hazardous Wastes with Advanced Clean Coal Technology By-Products.'' This report describes the activities of the project team during the reporting period. The principal work has focused upon new laboratory evaluation of samples from Phase 1, discussions with MAX Environmental Technologies, Inc., on the field work of Phase 2, preparing presentations, and making and responding to two outside contacts.

  7. Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality, August 2012

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn April 23, 2014, anEnergy nepdg_5251_5500.pdfAnalysis of Downwash fromWaste Treatment

  8. State-of-the-art of liquid waste disposal for geothermal energy systems: 1979. Report PNL-2404

    SciTech Connect (OSTI)

    Defferding, L.J.

    1980-06-01T23:59:59.000Z

    The state-of-the-art of geothermal liquid waste disposal is reviewed and surface and subsurface disposal methods are evaluated with respect to technical, economic, legal, and environmental factors. Three disposal techniques are currently in use at numerous geothermal sites around the world: direct discharge into surface waters; deep-well injection; and ponding for evaporation. The review shows that effluents are directly discharged into surface waters at Wairakei, New Zealand; Larderello, Italy; and Ahuachapan, El Salvador. Ponding for evaporation is employed at Cerro Prieto, Mexico. Deep-well injection is being practiced at Larderello; Ahuachapan; Otake and Hatchobaru, Japan; and at The Geysers in California. All sites except Ahuachapan (which is injecting only 30% of total plant flow) have reported difficulties with their systems. Disposal techniques used in related industries are also reviewed. The oil industry's efforts at disposal of large quantities of liquid effluents have been quite successful as long as the effluents have been treated prior to injection. This study has determined that seven liquid disposal methods - four surface and three subsurface - are viable options for use in the geothermal energy industry. However, additional research and development is needed to reduce the uncertainties and to minimize the adverse environmental impacts of disposal. (MHR)

  9. Microwave-assisted chemical process for treatment of hazardous waste: Annual report

    SciTech Connect (OSTI)

    Varma, R.; Nandi, S.P.; Cleaveland, D.C.

    1987-10-01T23:59:59.000Z

    Microwave energy provides rapid in situ uniform heating and can be used to initiate chemical processes at moderate temperatures. We investigate the technical feasibility of microwave-assisted chemical processes for detoxification of liquid hazardous waste. Trichloroethylene, a major constituent of waste streams, was selected for this detoxification study. Experiments were performed to investigate the oxidative degradation of trichloroethylene over active carbons (with and without catalysts) in air streams with microwave in situ heating, and to examine the feasibility of regenerating the used carbons. This study established that trichloroethylene in a vapor stream can be adsorbed at room temperature on active carbon beds that are loaded with Cu and Cr catalysts. When the bed is heated by a microwave radiation to moderate temperatures (<400/sup 0/C) while a moist air stream is passed through it, the trichloroethylene is readily converted into less-noxious products such as HCl, CO, CO/sub 2/ and C/sub 2/H/sub 2/Cl/sub 2/. Conversion higher than 80% was observed. Furthermore, the used carbon bed can be conveniently regenerated by microwave heating while a moist-N/sub 2/ or moist-air stream is passed through the bed. 4 refs., 5 figs., 10 tabs.

  10. Idaho Waste Vitrification Facilities Project Vitrified Waste Interim Storage Facility

    SciTech Connect (OSTI)

    Bonnema, Bruce Edward

    2001-09-01T23:59:59.000Z

    This feasibility study report presents a draft design of the Vitrified Waste Interim Storage Facility (VWISF), which is one of three subprojects of the Idaho Waste Vitrification Facilities (IWVF) project. The primary goal of the IWVF project is to design and construct a treatment process system that will vitrify the sodium-bearing waste (SBW) to a final waste form. The project will consist of three subprojects that include the Waste Collection Tanks Facility, the Waste Vitrification Facility (WVF), and the VWISF. The Waste Collection Tanks Facility will provide for waste collection, feed mixing, and surge storage for SBW and newly generated liquid waste from ongoing operations at the Idaho Nuclear Technology and Engineering Center. The WVF will contain the vitrification process that will mix the waste with glass-forming chemicals or frit and turn the waste into glass. The VWISF will provide a shielded storage facility for the glass until the waste can be disposed at either the Waste Isolation Pilot Plant as mixed transuranic waste or at the future national geological repository as high-level waste glass, pending the outcome of a Waste Incidental to Reprocessing determination, which is currently in progress. A secondary goal is to provide a facility that can be easily modified later to accommodate storage of the vitrified high-level waste calcine. The objective of this study was to determine the feasibility of the VWISF, which would be constructed in compliance with applicable federal, state, and local laws. This project supports the Department of Energy’s Environmental Management missions of safely storing and treating radioactive wastes as well as meeting Federal Facility Compliance commitments made to the State of Idaho.

  11. ENVIRONMENTAL IMPACTS ASSOCIATED WITH STORAGE, TREATMENT, AND DISPOSAL OF SOLID RADIOACTIVE AND CHEMICALLY HAZARDOUS WASTE AT THE HANFORD SITE, RICHLAND, WASHINGTON

    SciTech Connect (OSTI)

    Johnson, Wayne L.; Nelson, Iral C.; Payson, David R.; Rhoads, Kathleen

    2004-03-01T23:59:59.000Z

    The Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement (HSW EIS) provides environmental and technical information concerning U.S. Department of Energy (DOE) proposed waste management practices for certain solid radioactive wastes at the Hanford Site through the year 2046. The HSW EIS covers four primary aspects of waste management at Hanford – storage, treatment, transportation, and disposal. It also addresses four types of solid waste – low-level waste, mixed low-level waste that contains both radioactive and chemically hazardous constituents, immobilized low-activity waste from processing Hanford tank waste, and transuranic waste. The HSW EIS was prepared to assist DOE in determining which specific Hanford Site facilities will continue to be used, will be modified, or need to be constructed, to safely treat, store, and dispose of these wastes.

  12. TECHNICAL ASSESSMENT OF BULK VITRIFICATION PROCESS & PRODUCT FOR TANK WASTE TREATMENT AT THE DEPARTMENT OF ENERGY HANFORD SITE

    SciTech Connect (OSTI)

    SCHAUS, P.S.

    2006-07-21T23:59:59.000Z

    At the U.S. Department of Energy (DOE) Hanford Site, the Waste Treatment Plant (WTP) is being constructed to immobilize both high-level waste (IUW) for disposal in a national repository and low-activity waste (LAW) for onsite, near-surface disposal. The schedule-controlling step for the WTP Project is vitrification of the large volume of LAW, current capacity of the WTP (as planned) would require 50 years to treat the Hanford tank waste, if the entire LAW volume were to be processed through the WTP. To reduce the time and cost for treatment of Hanford Tank Waste, and as required by the Tank Waste Remediation System Environmental Impact Statement Record of Decision and the Hanford Federal Facility Consent Agreement (Tn-Party Agreement), DOE plans to supplement the LAW treatment capacity of the WTP. Since 2002, DOE, in cooperation with the Environmental Protection Agency and State of Washington Department of Ecology has been evaluating technologies that could provide safe and effective supplemental treatment of LAW. Current efforts at Hanford are intended to provide additional information to aid a joint agency decision on which technology will be used to supplement the WTP. A Research, Development and Demonstration permit has been issued by the State of Washington to build and (for a limited time) operate a Demonstration Bulk Vitrification System (DBVS) facility to provide information for the decision on a supplemental treatment technology for up to 50% of the LAW. In the Bulk Vitrification (BV) process, LAW, soil, and glass-forming chemicals are mixed, dried, and placed in a refractory-lined box, Electric current, supplied through two graphite electrodes in the box, melts the waste feed, producing a durable glass waste-form. Although recent modifications to the process have resulted in significant improvements, there are continuing technical concerns.

  13. Advanced and developmental technologies for treatment and volume reduction of dry active wastes

    SciTech Connect (OSTI)

    Kohout, R. [R. Kohout & Associates, Ltd., Toronto (Canada)

    1994-12-31T23:59:59.000Z

    The nuclear power industry processes Dry Active Wastes (DAW) to achieve cost-effective volume reduction and/or to produce a residue that is more compatible with final disposal criteria. The two principal processes currently used by the industry are compaction and incineration. Although incineration is often considered the process of choice, capital and operating cost are often high, and in some countries, public opposition and lengthy permitting processes result in expensive delays to bringing the process to operation. Therefore, alternative treatment options (mechanical, thermal, chemical, and biological) are being investigated to provide timely, cost-effective options for industry use. An overview of those developmental processes considered applicable to processing DAW is presented. In each category, {open_quotes}established{close_quotes} processes are mentioned and/or referenced, but the focus is on {open_quotes}potential{close_quotes} technologies and the status of their development. The emphasis is on processing DAW, and therefore, those developmental processes that primarily treat solids in aqueous streams and melting/sintering technologies, both of lesser applicability to nuclear utility wastes, have been omitted. Included are those developmental technologies that appear to have a potential for radioactive waste application based on development on demonstration programs.

  14. Reaction of Antimony-Uranium Composite Oxide in the Chlorination Treatment of Waste Catalyst - 13521

    SciTech Connect (OSTI)

    Sawada, Kayo [EcoTopia Science Institute (Japan)] [EcoTopia Science Institute (Japan); Hirabayashi, Daisuke; Enokida, Youichi [Department of Materials, Physics and Energy Engineering, Nagoya University, Furo-cho, Chikusa-ku, Nagoya, Aichi 464-8603 (Japan)] [Department of Materials, Physics and Energy Engineering, Nagoya University, Furo-cho, Chikusa-ku, Nagoya, Aichi 464-8603 (Japan)

    2013-07-01T23:59:59.000Z

    The effect of oxygen gas concentration on the chlorination treatment of antimony-uranium composite oxide catalyst waste was investigated by adding different concentrations of oxygen at 0-6 vol% to its chlorination agent of 0.6 or 6 vol% hydrogen chloride gas at 1173 K. The addition of oxygen tended to prevent the chlorination of antimony in the oxide. When 6 vol% hydrogen chloride gas was used, the addition of oxygen up to 0.1 vol% could convert the uranium contained in the catalyst to U{sub 3}O{sub 8} without any significant decrease in the reaction rate compared to that of the treatment without oxygen. (authors)

  15. Application of advanced liquid metal reactors to the destruction of radioactive wastes

    SciTech Connect (OSTI)

    Karnesky, R.A.; Dobbin, K.D.; Jordheim, D.P.; Rawlins, J.A.; Wootan, D.W.

    1991-08-01T23:59:59.000Z

    The ability of a small fast reactor to destroy hazardous long lived minor actinide and fission product wastes is evaluated. It is determined that by using a novel technique wherein high energy neutrons leaking from the active core of the reactor are moderated by yttrium hydride located in the target assemblies, substantial amounts of long lived fission products can be destroyed and useful quantities of the beneficial isotope {sup 238}Pu can be produced by transmutation of the {sup 237}Np and {sub 241}Am minor actinide waste components. In addition it is shown that minor actinides recovered from spent Light Water Reactor fuel can be used to fuel such a reactor, increasing the amount of hazardous minor actinide and fission product wastes that can be destroyed. 9 refs., 4 figs., 2 tabs.

  16. Subsurface Planar Vitrification Treatment of Problematic TRU Wastes: Status of a Technology Demonstration Program

    SciTech Connect (OSTI)

    Morse, M.K.; Nowack, B.R.; Thompson, L.E. [AMEC, 1135 Jadwin Avenue, Richland, WA 99352 (United States)

    2006-07-01T23:59:59.000Z

    This paper provides a status of the In Situ Transuranic Waste Delineation and Removal Project in which the GeoMelt{sup R} Subsurface Planar Vitrification{sup TM} (SPV{sup TM}) process is being evaluated for the in situ treatment of burial sites containing remote handled mixed transuranic (TRU) waste. The GeoMelt{sup R} SPV{sup TM} process was invented and patented by Geosafe Corporation. AMEC holds the exclusive worldwide license to use this technology. The current project is part of a three-phase demonstration program to evaluate the effectiveness of the GeoMelt{sup R} SPV{sup TM} process to treat waste contained in vertical pipe units (VPUs) and caissons that were used for the disposal of remote handled transuranic wastes located at Hanford's 618-10 and 618-11 burial grounds. This project is being performed for the US Department of Energy (DOE) for use at the Hanford site and other DOE installations. The Phase I evaluation determined that removal and treatment of the 618-10/11 VPUs are beyond what can be safely accomplished using conventional excavation methods. Accordingly, a careful stepwise non-intrusive delineation approach and treatment using the GeoMelt{sup R} SPV{sup TM} technology, followed by removal, characterization, and disposal of the resulting inert vitrified mass was identified as the preferred alternative. Phase II of the project, which started in July 2004, included a full-scale non-radioactive demonstration of AMEC's GeoMelt{sup R} SPV{sup TM} process on a mock VPU configured to match the actual VPUs. The non-radioactive demonstration (completed in May 2005) was performed to confirm the approach and design before proceeding to a radioactive ('hot') demonstration on an actual VPU. This demonstration took approximately 130 hours, processed the entire mock VPU, and resulted in a vitrified monolith weighing an estimated 90 tonnes. [1] Plans for a radioactive demonstration on an actual VPU are being developed for CY 2006. In addition to demonstrating GeoMelt{sup R} SPV{sup TM}, delineation techniques are being evaluated as part of the project to confirm the locations of the actual VPUs and to progressively determine their physical and chemical contents. The initial calibration and testing activities were completed in December 2005. The techniques included non-intrusive geophysical measurements from adjacent boreholes (ground penetrating radar, neutron-gamma radiography, etc.). Other methods available for use, on an as needed basis, include gas headspace sampling and boro-scope examinations inside the VPUs/caissons. (authors)

  17. Dilution and dispersion of liquid wastes in the Gulf of Mexico

    E-Print Network [OSTI]

    Beckett, Daniel Edward

    1974-01-01T23:59:59.000Z

    Sanctuaries Act of 1972, however, the Environmental Protection Agency (EPA) has been designated to oversee the barging of these wastes to sea. Thus, before a discharger can legally discharge in the ocean, he must acquire a permit from the EPA to do so. Data... legislation to provide any form of regulation of waste disposal practices. The Rivers and Harbors Act of 1899 prohi- bited the dumping of unauthorized materials into the navigable waters of the United States. This Act was originally designed to prevent...

  18. Corrosion Control Measures For Liquid Radioactive Waste Storage Tanks At The Savannah River Site

    SciTech Connect (OSTI)

    Wiersma, B. J.; Subramanian, K. H.

    2012-11-27T23:59:59.000Z

    The Savannah River Site has stored radioactive wastes in large, underground, carbon steel tanks for approximately 60 years. An assessment of potential degradation mechanisms determined that the tanks may be vulnerable to nitrate- induced pitting corrosion and stress corrosion cracking. Controls on the solution chemistry and temperature of the wastes are in place to mitigate these mechanisms. These controls are based upon a series of experiments performed using simulated solutions on materials used for construction of the tanks. The technical bases and evolution of these controls is presented in this paper.

  19. Selection of Steady-State Process Simulation Software to Optimize Treatment of Radioactive and Hazardous Waste

    SciTech Connect (OSTI)

    Nichols, T. T.; Barnes, C. M.; Lauerhass, L.; Taylor, D. D.

    2001-06-01T23:59:59.000Z

    The process used for selecting a steady-state process simulator under conditions of high uncertainty and limited time is described. Multiple waste forms, treatment ambiguity, and the uniqueness of both the waste chemistries and alternative treatment technologies result in a large set of potential technical requirements that no commercial simulator can totally satisfy. The aim of the selection process was two-fold. First, determine the steady-state simulation software that best, albeit not completely, satisfies the requirements envelope. And second, determine if the best is good enough to justify the cost. Twelve simulators were investigated with varying degrees of scrutiny. The candidate list was narrowed to three final contenders: ASPEN Plus 10.2, PRO/II 5.11, and CHEMCAD 5.1.0. It was concluded from ''road tests'' that ASPEN Plus appears to satisfy the project's technical requirements the best and is worth acquiring. The final software decisions provide flexibility: they involve annual rather than multi-year licensing, and they include periodic re-assessment.

  20. STATUS & DIRECTION OF THE BULK VITRIFICATION PROGRAM FOR THE SUPPLEMENTAL TREATMENT OF LOW ACTIVITY TANK WASTE AT HANFORD

    SciTech Connect (OSTI)

    RAYMOND, R.E.

    2005-01-12T23:59:59.000Z

    The DOE Office of River Protection (ORP) is managing a program at the Hanford site that will retrieve and treat more than 200 million liters (53 million gal.) of radioactive waste stored in underground storage tanks. The waste was generated over the past 50 years as part of the nation's defense programs. The project baseline calls for the waste to be retrieved from the tanks and partitioned to separate the highly radioactive constituents from the large volumes of chemical waste. These highly radioactive components will be vitrified into glass logs in the Waste Treatment Plant (WTP), temporarily stored on the Hanford Site, and ultimately disposed of as high-level waste in the offsite national repository. The less radioactive chemical waste, referred to as low-activity waste (LAW), is also planned to be vitrified by the WTP, and then disposed of in approved onsite trenches. However, additional treatment capacity is required in order to complete the pretreatment and immobilization of the tank waste by 2028, which represents a Tri-Party Agreement milestone. To help ensure that the treatment milestones will be met, the Supplemental Treatment Program was undertaken. The program, managed by CH2M HILL Hanford Group, Inc., involves several sub-projects each intended to supplement part of the treatment of waste being designed into the WTP. This includes the testing, evaluation, design, and deployment of supplemental LAW treatment and immobilization technologies, retrieval and treatment of mixed TRU waste stored in the Hanford Tanks, and supplemental pre-treatment. Applying one or more supplemental treatment technologies to the LAW has several advantages, including providing additional processing capacity, reducing the planned loading on the WTP, and reducing the need for double-shell tank space for interim storage of LAW. In fiscal year 2003, three potential supplemental treatment technologies were evaluated including grout, steam reforming and bulk vitrification using AMEC's In-Container Vitrification{trademark} process. As an outcome of this work, the hulk vitrification process was recommended for further evaluation. In fiscal year 2004, a follow-on bulk vitrification project was initiated to design, procure, assemble and operate a full-scale bulk vitrification pilot-plant to treat low activity tank waste from Hanford tank 241-S-109 under a Research, Development and Demonstration permit. That project is referred to as the Demonstration Bulk Vitrification System (or DBVS). The DBVS project will provide a full-scale bulk vitrification demonstration facility that can be used to assess the effectiveness of the bulk vitrification process under actual operating conditions. The pilot-plant is scheduled to commence operations in late 2005. The Supplemental Treatment Program represents a major element of the ORP's strategy to complete the pretreatment and immobilization of tank wastes by 2028. This paper will provide an overview of the bulk vitrification process and the progress in establishing the pilot-plant.

  1. Supplemental analysis of accident sequences and source terms for waste treatment and storage operations and related facilities for the US Department of Energy waste management programmatic environmental impact statement

    SciTech Connect (OSTI)

    Folga, S.; Mueller, C.; Nabelssi, B.; Kohout, E.; Mishima, J.

    1996-12-01T23:59:59.000Z

    This report presents supplemental information for the document Analysis of Accident Sequences and Source Terms at Waste Treatment, Storage, and Disposal Facilities for Waste Generated by US Department of Energy Waste Management Operations. Additional technical support information is supplied concerning treatment of transuranic waste by incineration and considering the Alternative Organic Treatment option for low-level mixed waste. The latest respirable airborne release fraction values published by the US Department of Energy for use in accident analysis have been used and are included as Appendix D, where respirable airborne release fraction is defined as the fraction of material exposed to accident stresses that could become airborne as a result of the accident. A set of dominant waste treatment processes and accident scenarios was selected for a screening-process analysis. A subset of results (release source terms) from this analysis is presented.

  2. THERMAL TREATMENT REVIEW . WTE I THERMAL TREATMENT Since the beginning of this century, global waste-to-energy capacity

    E-Print Network [OSTI]

    Columbia University

    of new waste-to gasification process at an industrial scale The Waste-To-Energy Research and Technology Council (WTERT), headquartered at Columbia University in New York City, keeps a close watch on the thermal waste-to-energy capacity has increased steadily at the rate of about four million tonnes of MSW per year

  3. FULL SCALE TESTING TECHNOLOGY MATURATION OF A THIN FILM EVAPORATOR FOR HIGH-LEVEL LIQUID WASTE MANAGEMENT AT HANFORD - 12125

    SciTech Connect (OSTI)

    TEDESCHI AR; CORBETT JE; WILSON RA; LARKIN J

    2012-01-26T23:59:59.000Z

    Simulant testing of a full-scale thin-film evaporator system was conducted in 2011 for technology development at the Hanford tank farms. Test results met objectives of water removal rate, effluent quality, and operational evaluation. Dilute tank waste simulant, representing a typical double-shell tank supernatant liquid layer, was concentrated from a 1.1 specific gravity to approximately 1.5 using a 4.6 m{sup 2} (50 ft{sup 2}) heated transfer area Rototherm{reg_sign} evaporator from Artisan Industries. The condensed evaporator vapor stream was collected and sampled validating efficient separation of the water. An overall decontamination factor of 1.2E+06 was achieved demonstrating excellent retention of key radioactive species within the concentrated liquid stream. The evaporator system was supported by a modular steam supply, chiller, and control computer systems which would be typically implemented at the tank farms. Operation of these support systems demonstrated successful integration while identifying areas for efficiency improvement. Overall testing effort increased the maturation of this technology to support final deployment design and continued project implementation.

  4. An Istrument for Measuring the TRU Concentration in High-Level Liquid Waste

    SciTech Connect (OSTI)

    Brodzinski, Ronald L.; Craig, R. A.; Fink, Samuel D.; Hensley, Walter K.; Holt, Noah O.; Knopf, Michael A.; Lepel, Elwood A.; Mullen, O Dennis; Salaymeh, Saleem R.; Samuel, Todd J.; Smart, John E.; Tinker, Michael R.; Walker, Darrell D.

    2005-02-01T23:59:59.000Z

    An online monitor has been designed, built, and tested, which is capable of measuring the residual transuranic concentrations in processed high-level wastes with a detection limit of 370 Bq/ml (10 nCi/ml) in less than six hours. The monitor measures the neutrons produced by the transuranics, primarily via (?,n) reactions, in the presence of gamma-ray fields up to 1 Sv/h (100 R/h). The optimum design was determined by Monte Carlo modeling and then tempered with practical engineering and cost considerations. Correct operation of the monitor was demonstrated in a hot cell utilizing an actual sample of high-level waste. Results of that demonstration are given, and suggestions for improvements in the next generation system are discussed.

  5. Isolation of Metals from Liquid Wastes: Reactive Scavenging in Turbulent Thermal Reactors

    SciTech Connect (OSTI)

    Jost O.L. Wendt; Alan R. Kerstein; Alexander Scheeline; Arne Pearlstein; William Linak

    2003-08-06T23:59:59.000Z

    The Overall project demonstrated that toxic metals (cesium Cs and strontium Sr) in aqueous and organic wastes can be isolated from the environment through reaction with kaolinite based sorbent substrates in high temperature reactor environments. In addition, a state-of-the art laser diagnostic tool to measure droplet characteristic in practical 'dirty' laboratory environments was developed, and was featured on the cover of a recent edition of the scientific journal ''applied Spectroscopy''. Furthermore, great strides have been made in developing a theoretical model that has the potential to allow prediction of the position and life history of every particle of waste in a high temperature, turbulent flow field, a very challenging problem involving as it does, the fundamentals of two phase turbulence and of particle drag physics.

  6. A Brief Review of Filtration Studies for Waste Treatment at the Hanford Site

    SciTech Connect (OSTI)

    Daniel, Richard C.; Schonewill, Philip P.; Shimskey, Rick W.; Peterson, Reid A.

    2010-12-01T23:59:59.000Z

    This document completes the requirements of Milestone 1-2, PNNL Draft Literature Review, discussed in the scope of work outlined in the EM-31 Support Project task plan WP-2.3.6-2010-1. The focus of task WP 2.3.6 is to improve the U.S. Department of Energy’s (DOE’s) understanding of filtration operations for high-level waste (HLW) to enhance filtration and cleaning efficiencies, thereby increasing process throughput and reducing the sodium demand (through acid neutralization). Developing the processes for fulfilling the cleaning/backpulsing requirements will result in more efficient operations for both the Hanford Tank Waste Treatment and Immobilization Plant (WTP) and the Savannah River Site (SRS), thereby increasing throughput by limiting cleaning cycles. The purpose of this document is to summarize Pacific Northwest National Laboratory’s (PNNL’s) literature review of historical filtration testing at the laboratory and of testing found in peer-reviewed journals. Eventually, the contents of this document will be merged with a literature review by SRS to produce a summary report for DOE of the results of previous filtration testing at the laboratories and the types of testing that still need to be completed to address the questions about improved filtration performance at WTP and SRS. To this end, this report presents 1) a review of the current state of crossflow filtration knowledge available in the peer-reviewed literature, 2) a detailed review of PNNL-related filtration studies specific to the Hanford site, and 3) an overview of current waste filtration models developed by PNNL and suggested avenues for future model development.

  7. Water treatment capacity of forward osmosis systems utilizing power plant waste heat

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Zhou, Xingshi; Gingerich, Daniel B.; Mauter, Meagan S.

    2015-06-11T23:59:59.000Z

    Forward osmosis (FO) has the potential to improve the energy efficiency of membrane-based water treatment by leveraging waste heat from steam electric power generation as the primary driving force for separation. In this study, we develop a comprehensive FO process model, consisting of membrane separation, heat recovery, and draw solute regeneration (DSR) models. We quantitatively characterize three alternative processes for DSR: distillation, steam stripping, and air stripping. We then construct a mathematical model of the distillation process for DSR that incorporates hydrodynamics, mass and heat transport resistances, and reaction kinetics, and we integrate this into a model for the fullmore »FO process. Finally, we utilize this FO process model to derive a first-order approximation of the water production capacity given the rejected heat quantity and quality available at U.S. electric power facilities. We find that the upper bound of FO water treatment capacity using low-grade heat sources at electric power facilities exceeds process water treatment demand for boiler water make-up and flue gas desulfurization wastewater systems.« less

  8. Water treatment capacity of forward osmosis systems utilizing power plant waste heat

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Zhou, Xingshi [Carnegie Mellon Univ., Pittsburgh, PA (United States); Gingerich, Daniel B. [Carnegie Mellon Univ., Pittsburgh, PA (United States); Mauter, Meagan S. [Carnegie Mellon Univ., Pittsburgh, PA (United States)

    2015-06-11T23:59:59.000Z

    Forward osmosis (FO) has the potential to improve the energy efficiency of membrane-based water treatment by leveraging waste heat from steam electric power generation as the primary driving force for separation. In this study, we develop a comprehensive FO process model, consisting of membrane separation, heat recovery, and draw solute regeneration (DSR) models. We quantitatively characterize three alternative processes for DSR: distillation, steam stripping, and air stripping. We then construct a mathematical model of the distillation process for DSR that incorporates hydrodynamics, mass and heat transport resistances, and reaction kinetics, and we integrate this into a model for the full FO process. Finally, we utilize this FO process model to derive a first-order approximation of the water production capacity given the rejected heat quantity and quality available at U.S. electric power facilities. We find that the upper bound of FO water treatment capacity using low-grade heat sources at electric power facilities exceeds process water treatment demand for boiler water make-up and flue gas desulfurization wastewater systems.

  9. One System Integrated Project Team Progress in Coordinating Hanford Tank Farms and the Waste Treatment Plant

    SciTech Connect (OSTI)

    Skwarek, Raymond J. [Washington River Protection Systems, Richland, WA (United States); Harp, Ben J. [USDOE Office of River Protection, Richland, WA (United States); Duncan, Garth M. [Bechtel National, Inc. (United States)

    2013-12-18T23:59:59.000Z

    The One System Integrated Project Team (IPT) was formed at the Hanford Site in late 2011 as a way to improve coordination and itegration between the Hanford Tank Waste Treatment and Immobilization Plant (WTP) and the Tank Operations Contractor (TOC) on interfaces between the two projects, and to eliminate duplication and exploit opportunities for synergy. The IPT is composed of jointly staffed groups that work on technical issues of mutal interest, front-end design and project definition, nuclear safety, plant engineering system integration, commissioning, planning and scheduling, and environmental, safety, health and quality (ESH&Q) areas. In the past year important progress has been made in a number of areas as the organization has matured and additional opportunities have been identified. Areas covered in this paper include: Support for development of the Office of Envirnmental Management (EM) framework document to progress the Office of River Protection's (ORP) River Protection Project (RPP) mission; Stewardship of the RPP flowsheet; Collaboration with Savannah River Site (SRS), Savannah River National Laboratory (SRNL), and Pacific Northwest National Laboratory (PNNL); Operations programs integration; and, Further development of the waste acceptance criteria.

  10. Resource Conservation and Recovery Act (RCRA) Closure Plan Summary for Interim reasctive Waste Treatment Area (IRWTA)

    SciTech Connect (OSTI)

    Collins, E.T.

    1997-07-01T23:59:59.000Z

    This closure plan has been prepared for the interim Reactive Waste Treatment Area (IRWT'A) located at the Y-12 Pkmt in oak Ridge, Tennessee (Environmental Protection Agency [EPA] Identification TN 389-009-0001). The actions required to achieve closure of the IRWTA are outlined in this plan, which is being submitted in accordance with Tennessee Ruie 1200- 1-1 1-.0S(7) and Title 40, Code of Federal Regulations (CFR), Part 265, Subpart G. The IRWTA was used to treat waste sodium and potassium (NaK) that are regulated by the Resource Conservation and Recovery Act (RCRA). The location of the IRWT'A is shown in Figures 1 and 2, and a diagram is shown in Figure 3. This pkm details all steps that wdi be petiormed to close the IRWTA. Note that this is a fmai ciosure.and a diagram is shown in Figure 3. This pkm details all steps that wdi be petiormed to close the IRWTA. Note that this is a fmai ciosure.

  11. Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

    SciTech Connect (OSTI)

    Neupauer, R.M.; Thurmond, S.M.

    1992-09-01T23:59:59.000Z

    This report describes health and safety concerns associated with the Mixed and Low-level Waste Treatment Facility at the Idaho National Engineering Laboratory. Various hazards are described such as fire, electrical, explosions, reactivity, temperature, and radiation hazards, as well as the potential for accidental spills, exposure to toxic materials, and other general safety concerns.

  12. Determination of vapor-liquid equilibrium data and decontamination factors needed for the development of evaporator technology for use in volume reduction of radioactive waste streams

    SciTech Connect (OSTI)

    Betts, S.E. [California Univ., Santa Barbara, CA (United States)

    1993-10-01T23:59:59.000Z

    A program is currently in progress at Argonne National Laboratory to evaluate and develop evaporator technology for concentrating radioactive waste streams. By concentrating radioactive waste streams, disposal costs can be significantly reduced. To effectively reduce the volume of waste, the evaporator must achieve high decontamination factors so that the distillate is sufficiently free of radioactive material. One technology that shows a great deal of potential for this application is being developed by LICON, Inc. In this program, Argonne plans to apply LICON`s evaporator designs to the processing of radioactive solutions. Concepts that need to be incorporated into the design of the evaporator include, criticality safety, remote operation and maintenance, and materials of construction. To design an effective process for concentrating waste streams, both solubility and vapor-liquid equilibrium data are needed. The key issue, however, is the high decontamination factors that have been demonstrated by this equipment. Two major contributions were made to this project. First, a literature survey was completed to obtain available solubility and vapor-liquid equilibrium data. Some vapor-liquid data necessary for the project but not available in the literature was obtained experimentally. Second, the decontamination factor for the evaporator was determined using neutron activation analysis (NAA).

  13. Department of Energy Idaho Operations Office evaluation of feasibility studies for private sector treatment of alpha and TRU mixed wastes

    SciTech Connect (OSTI)

    NONE

    1995-05-01T23:59:59.000Z

    The Idaho National Engineering Laboratory (INEL) is currently storing a large quantity of alpha contaminated mixed low level waste which will require treatment prior to disposal. The DOE Idaho Operations Office (DOE-ID) recognized that current knowledge and funding were insufficient to directly pursue services for the requisite treatment. Therefore, it was decided that private sector studies would be funded to clarify cost, regulatory, technology, and contractual issues associated with procuring treatment services. This report analyzes the three private sector studies procured and recommends a path forward for DOE in procuring retrieval, assay, characterization, and treatment services for INEL transuranic and alpha contaminated mixed low level waste. This report was prepared by a team of subject matter experts from the INEL referred to as the DOE-ID Evaluation Team.

  14. Development and results of experimental testing of electromembrane process for liquid active waste purification

    SciTech Connect (OSTI)

    Martinov, B.V.; Smirnov, V.V.; Tugolukov, B.B.; Belyakov, Y.A. [A.A. Bochvar All Russian Scientific Research, Moscow (Russian Federation). Inst. of Inorganic Materials

    1993-12-31T23:59:59.000Z

    This paper discusses the results of studies on electromembrane purification. The concentration of salts in active wastes arising from decontamination is more than 3--5 g/l. For these investigations a solution was chosen that had arisen from the decontamination of metallic items by a two-bath method using permanganate-alkali in the first stage and nitrogen oxalic acid in the second stage. The total salt content of mixed acid and alkaline solutions was 3.0 g/l, with a pH of 8.5 and total beta-activity of 6 {times} 10{sup {minus}8} Ci/l.

  15. Home and community composting for on-site treatment of urban organic waste: perspective for Europe and Canada

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Home and community composting for on-site treatment of urban organic waste: perspective for Europe practice (Base Sce), this paper examines on-site UOW composting strategies using a combination of centralized composting facilities (CCF), community composting centres (CCC) and home composting (HC) (Sce 1, 2

  16. Waste treatment process for removal of contaminants from aqueous, mixed-waste solutions using sequential chemical treatment and crossflow microfiltration, followed by dewatering

    DOE Patents [OSTI]

    Vijayan, Sivaraman (Deep River, CA); Wong, Chi F. (Pembroke, CA); Buckley, Leo P. (Deep River, CA)

    1994-01-01T23:59:59.000Z

    In processes of this invention aqueous waste solutions containing a variety of mixed waste contaminants are treated to remove the contaminants by a sequential addition of chemicals and adsorption/ion exchange powdered materials to remove the contaminants including lead, cadmium, uranium, cesium-137, strontium-85/90, trichloroethylene and benzene, and impurities including iron and calcium. Staged conditioning of the waste solution produces a polydisperse system of size enlarged complexes of the contaminants in three distinct configurations: water-soluble metal complexes, insoluble metal precipitation complexes, and contaminant-bearing particles of ion exchange and adsorbent materials. The volume of the waste is reduced by separation of the polydisperse system by cross-flow microfiltration, followed by low-temperature evaporation and/or filter pressing. The water produced as filtrate is discharged if it meets a specified target water quality, or else the filtrate is recycled until the target is achieved.

  17. Waste treatment process for removal of contaminants from aqueous, mixed-waste solutions using sequential chemical treatment and crossflow microfiltration, followed by dewatering

    DOE Patents [OSTI]

    Vijayan, S.; Wong, C.F.; Buckley, L.P.

    1994-11-22T23:59:59.000Z

    In processes of this invention aqueous waste solutions containing a variety of mixed waste contaminants are treated to remove the contaminants by a sequential addition of chemicals and adsorption/ion exchange powdered materials to remove the contaminants including lead, cadmium, uranium, cesium-137, strontium-85/90, trichloroethylene and benzene, and impurities including iron and calcium. Staged conditioning of the waste solution produces a polydisperse system of size enlarged complexes of the contaminants in three distinct configurations: water-soluble metal complexes, insoluble metal precipitation complexes, and contaminant-bearing particles of ion exchange and adsorbent materials. The volume of the waste is reduced by separation of the polydisperse system by cross-flow microfiltration, followed by low-temperature evaporation and/or filter pressing. The water produced as filtrate is discharged if it meets a specified target water quality, or else the filtrate is recycled until the target is achieved. 1 fig.

  18. Isolation of Metals from Liquid Wastes: Reactive Scavenging in Turbulent Thermal Reactors

    SciTech Connect (OSTI)

    William Linak

    2004-12-16T23:59:59.000Z

    Sorption of cesium and strontium on kaolinite powders was investigated as a means to minimize the emissions of these metals during certain high temperature processes currently being developed to isolate and dispose of radiological and mixed wastes. In this work, non-radioactive aqueous cesium acetate or strontium acetate was atomized down the center of a natural gas flame supported on a variable-swirl burner in a refractory-lined laboratory-scale combustion facility. Kaolinite powder was injected at a post-flame location in the combustor. Cesium readily vaporizes in the high temperature regions of the combustor, but was reactively scavenged onto dispersed kaolinite. Global sorption mechanisms of cesium vapor on kaolinite were quantified, and are related to those available in the literature for sodium and lead. Both metal adsorption and substrate deactivation steps are important, and so there is an optimum temperature, between 1400 and 1500 K, at which maximum sorption occurs. The presence of chlorine inhibits cesium sorption. In contrast to cesium, and in the absence of chlorine, strontium was only partially vaporized and was, therefore, only partially scavengeable. The strontium data did not allow quantification of global kinetic mechanisms of interaction, although equilibrium arguments provided insight into the effects of chlorine on strontium sorption. These results have implications for the use of sorbents to control cesium and strontium emissions during high temperature waste processing including incineration and vitrification.

  19. Removal of hydrogen sulfide from waste treatment plant biogas using the apollo scrubber

    SciTech Connect (OSTI)

    Smith, J.W.; Burrowes, P.A.; Gupta, A.; Walton, P.S.; Meffe, S.

    1996-12-31T23:59:59.000Z

    The removal of hydrogen sulfide and other sulphur compounds from anaerobic digester gas streams prior to their use as fuel for boilers, stationary engines, and cogeneration units minimizes corrosion problems and reduces sulfur emission loadings. A research program at the Department of Chemical Engineering and Applied Chemistry, University of Toronto in the 1980`s demonstrated the use of a modified flotation cell for the absorption of hydrogen sulfide from a gas stream and its catalytic oxidation to sulfur. The essence of the technology was a proprietary gas liquid contactor which provided very high mass transfer rates at the interface. A bench scale contactor developed at the university achieved hydrogen sulfide removal efficiencies of over 99.9% at atmospheric pressure. A demonstration unit for digester gas scrubbing applications was designed, fabricated, and then installed and evaluated at the Metropolitan Toronto Works Department - Main Treatment Plant (MTP).

  20. Structural Integrity Program for the 300,000-Gallon Radioactive Liquid Waste Storage Tanks at the Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    Bryant, J.W.; Nenni, J.A.; Yoder, T.S.

    2003-04-22T23:59:59.000Z

    This report provides a record of the Structural Integrity Program for the 300,000-gal liquid waste storage tanks and associated equipment at the Idaho Nuclear Technology and Engineering Center, as required by U.S. Department of Energy M 435.1-1, ''Radioactive Waste Management Manual.'' This equipment is known collectively as the Tank Farm Facility. The conclusion of this report is that the Tank Farm Facility tanks, vaults, and transfer systems that remain in service for storage are structurally adequate, and are expected to remain structurally adequate over the remainder of their planned service life through 2012. Recommendations are provided for continued monitoring of the Tank Farm Facility.

  1. Structural Integrity Program for the 300,000-Gallon Radioactive Liquid Waste Tanks at the Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    Bryant, Jeffrey Whealdon; Nenni, Joseph A; Timothy S. Yoder

    2003-04-01T23:59:59.000Z

    This report provides a record of the Structural Integrity Program for the 300,000-gal liquid waste storage tanks and associated equipment at the Idaho Nuclear Technology and Engineering Center, as required by U.S. Department of Energy M 435.1-1, “Radioactive Waste Management Manual.” This equipment is known collectively as the Tank Farm Facility. The conclusion of this report is that the Tank Farm Facility tanks, vaults, and transfer systems that remain in service for storage are structurally adequate, and are expected to remain structurally adequate over the remainder of their planned service life through 2012. Recommendations are provided for continued monitoring of the Tank Farm Facility.

  2. Cross flow filtration of aqueous radioactive tank wastes

    SciTech Connect (OSTI)

    McCabe, D.J. [Westinghouse Savannah River Co., Aiken, SC (United States); Reynolds, B.A. [Battelle Pacific Northwest Lab., Richland, WA (United States); Todd, T.A. [Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States); Wilson, J.H. [Oak Ridge National Lab., TN (United States)

    1997-02-01T23:59:59.000Z

    The Tank Focus Area (TFA) of the Department of Energy (DOE) Office of Science and Technology addresses remediation of radioactive waste currently stored in underground tanks. Baseline technologies for treatment of tank waste can be categorized into three types of solid liquid separation: (a) removal of radioactive species that have been absorbed or precipitated, (b) pretreatment, and (c) volume reduction of sludge and wash water. Solids formed from precipitation or absorption of radioactive ions require separation from the liquid phase to permit treatment of the liquid as Low Level Waste. This basic process is used for decontamination of tank waste at the Savannah River Site (SRS). Ion exchange of radioactive ions has been proposed for other tank wastes, requiring removal of insoluble solids to prevent bed fouling and downstream contamination. Additionally, volume reduction of washed sludge solids would reduce the tank space required for interim storage of High Level Wastes. The scope of this multi-site task is to evaluate the solid/liquid separations needed to permit treatment of tank wastes to accomplish these goals. Testing has emphasized cross now filtration with metal filters to pretreat tank wastes, due to tolerance of radiation and caustic.

  3. Method for solidification of radioactive and other hazardous waste

    DOE Patents [OSTI]

    Anshits, Alexander G. (Krasnoyarsk, RU); Vereshchagina, Tatiana A. (Krasnoyarsk, RU); Voskresenskaya, Elena N. (Krasnoyarsk, RU); Kostin, Eduard M. (Zheleznogorsk, RU); Pavlov, Vyacheslav F. (Krasnoyarsk, RU); Revenko, Yurii A. (Zheleznogorsk, RU); Tretyakov, Alexander A. (Zheleznogorsk, RU); Sharonova, Olga M. (Krasnoyarsk, RU); Aloy, Albert S. (Saint-Petersburg, RU); Sapozhnikova, Natalia V. (Saint-Petersburg, RU); Knecht, Dieter A. (Idaho Falls, ID); Tranter, Troy J. (Idaho Falls, ID); Macheret, Yevgeny (Idaho Falls, ID)

    2002-01-01T23:59:59.000Z

    Solidification of liquid radioactive waste, and other hazardous wastes, is accomplished by the method of the invention by incorporating the waste into a porous glass crystalline molded block. The porous block is first loaded with the liquid waste and then dehydrated and exposed to thermal treatment at 50-1,000.degree. C. The porous glass crystalline molded block consists of glass crystalline hollow microspheres separated from fly ash (cenospheres), resulting from incineration of fossil plant coals. In a preferred embodiment, the porous glass crystalline blocks are formed from perforated cenospheres of grain size -400+50, wherein the selected cenospheres are consolidated into the porous molded block with a binder, such as liquid silicate glass. The porous blocks are then subjected to repeated cycles of saturating with liquid waste, and drying, and after the last cycle the blocks are subjected to calcination to transform the dried salts to more stable oxides. Radioactive liquid waste can be further stabilized in the porous blocks by coating the internal surface of the block with metal oxides prior to adding the liquid waste, and by coating the outside of the block with a low-melting glass or a ceramic after the waste is loaded into the block.

  4. Development Of A Macro-Batch Qualification Strategy For The Hanford Tank Waste Treatment And Immobilization Plant

    SciTech Connect (OSTI)

    Herman, Connie C.

    2013-09-30T23:59:59.000Z

    The Savannah River National Laboratory (SRNL) has evaluated the existing waste feed qualification strategy for the Hanford Tank Waste Treatment and Immobilization Plant (WTP) based on experience from the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) waste qualification program. The current waste qualification programs for each of the sites are discussed in the report to provide a baseline for comparison. Recommendations on strategies are then provided that could be implemented at Hanford based on the successful Macrobatch qualification strategy utilized at SRS to reduce the risk of processing upsets or the production of a staged waste campaign that does not meet the processing requirements of the WTP. Considerations included the baseline WTP process, as well as options involving Direct High Level Waste (HLW) and Low Activity Waste (LAW) processing, and the potential use of a Tank Waste Characterization and Staging Facility (TWCSF). The main objectives of the Hanford waste feed qualification program are to demonstrate compliance with the Waste Acceptance Criteria (WAC), determine waste processability, and demonstrate unit operations at a laboratory scale. Risks to acceptability and successful implementation of this program, as compared to the DWPF Macro-Batch qualification strategy, include: Limitations of mixing/blending capability of the Hanford Tank Farm; The complexity of unit operations (i.e., multiple chemical and mechanical separations processes) involved in the WTP pretreatment qualification process; The need to account for effects of blending of LAW and HLW streams, as well as a recycle stream, within the PT unit operations; and The reliance on only a single set of unit operations demonstrations with the radioactive qualification sample. This later limitation is further complicated because of the 180-day completion requirement for all of the necessary waste feed qualification steps. The primary recommendations/changes include the following: Collection and characterization of samples for relevant process analytes from the tanks to be blended during the staging process; Initiation of qualification activities earlier in the staging process to optimize the campaign composition through evaluation from both a processing and glass composition perspective; Definition of the parameters that are important for processing in the WTP facilities (unit operations) across the anticipated range of wastes and as they relate to qualification-scale equipment; Performance of limited testing with simulants ahead of the waste feed qualification sample demonstration as needed to determine the available processing window for that campaign; and Demonstration of sufficient mixing in the staging tank to show that the waste qualification sample chemical and physical properties are representative of the transfers to be made to WTP. Potential flowcharts for derivatives of the Hanford waste feed qualification process are also provided in this report. While these recommendations are an extension of the existing WTP waste qualification program, they are more in line with the processes currently performed for SRS. The implementation of these processes at SRS has been shown to offer flexibility for processing, having identified potential processing issues ahead of the qualification or facility processing, and having provided opportunity to optimize waste loading and throughput in the DWPF.

  5. Waste management project fiscal year 1998 multi-year work plan WBS 1.2

    SciTech Connect (OSTI)

    Slaybaugh, R.R.

    1997-08-29T23:59:59.000Z

    The MYWP technical baseline describes the work to be accomplished by the Project and the technical standards which govern that work. The Waste Management Project manages and integrates (non-TWRS) waste management activities at the site. Activities include management of Hanford wastes as well as waste transferred to Hanford from other DOE, Department of Defense, or other facilities. This work includes handling, treatment, storage, and disposition of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project (SW), Liquid Effluents Project (LEP), and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible. The paper tabulates the major facilities that interface with this Project, identifying the major facilities that generate waste, materials, or infrastructure for this Project and the major facilities that will receive waste and materials from this Project.

  6. Comparison between CMPO and DHDECMP for alpha decontamination of radioactive liquid waste

    SciTech Connect (OSTI)

    Muscatello, A.C.; Yarbro, S.L.; Marsh, S.F.

    1990-01-01T23:59:59.000Z

    Ion exchange is the major method used at Los Alamos to recover and purify plutonium from a variety of different contaminants. During this process, a high-acid (5-7M), low-activity stream is produced that presently is concentrated by evaporation, then cemented for long-term disposal. Our goal is to remove and concentrate the radioactive elements so that the remainder can be treated as low-level'' or regular industrial waste. Solvent extraction with neutral bifunctional extractants, such as DHDECMP and CMPO, has been chosen as the process to be developed. Experimental work has shown that both extractants effectively remove actinides to below the required limits, but that CMPO was much more difficult to strip. In addition, studies of plutonium and americium removal using a wide variety of ion exchangers and supported extractants including DHDECMP, CMPO, and TOPO will be reviewed. 22 refs., 10 figs., 3 tabs.

  7. An Instrument for Measuring the TRU Concentration in High-Level Liquid Waste

    SciTech Connect (OSTI)

    Brodzinski, Ronald L.; Craig, R A.; Fink, Samuel D.; Hensley, Walter K.; Holt, Noah OA; Knopf, Michael A.; Lepel, Elwood A.; Mullen, O Dennis; Salaymeh, Saleem R.; Samuel, Todd J.; Smart, John E.; Tinker, Mike R.; Walker, D

    2005-02-01T23:59:59.000Z

    An online monitor has been designed, built, and tested that is capable of measuring the residual transuranic concentrations in processed high-level wastes with a detection limit of 370 Bq/ml (10 nCi/ml) in less than six hours. The monitor measures the ({alpha},n) neutrons in the presence of gamma-ray fields up to 1 Sv/h (100 R/h). The optimum design was determined by Monte Carlo modeling and then tempered with practical engineering and cost considerations. A multiplicity counter is used in data acquisition to reject the large fraction of coincident and highly variable cosmic-ray-engendered background events and results in a S/N ratio {approx}1.

  8. CONDITIONING TECHNOLOGY FOR RADIOACTIVE WASTE RESULTED FROM THE TREATMENT OF LIQUID WASTE FROM THE ROMANIAN NUCLEAR POWER PLANT

    SciTech Connect (OSTI)

    ARSENE, CARMEN; ANDREI, VERONICA; NEGOIU, DUMITRU

    2003-02-27T23:59:59.000Z

    For the conditioning of spent resins contaminated with radionuclides, such as: 137Cs, 134Cs, 60Co, 58Co, 57Co, 54Mn, etc., techniques of direct immobilization in cement, bitumen and organic polymers have been tested. The selected process was the bituminization using industrial bitumen, I 60-70, made in Romania, which had very good characteristics. The paper presents stages of the research project, technical conditions for the process and advantages of the bituminization of spent resins.

  9. The Use of Induction Melting for the Treatment of Metal Radioactive Waste - 13088

    SciTech Connect (OSTI)

    Zherebtsov, Alexander; Pastushkov, Vladimir; Poluektov, Pavel; Smelova, Tatiana; Shadrin, Andrey [JSC 'VNIINM', Rogova st., 5, 123098, Moscow (Russian Federation)] [JSC 'VNIINM', Rogova st., 5, 123098, Moscow (Russian Federation)

    2013-07-01T23:59:59.000Z

    The aim of the work is to assess the efficacy of induction melting metal for recycling radioactive waste in order to reduce the volume of solid radioactive waste to be disposed of, and utilization of the metal. (authors)

  10. Solid Waste Management Written Program

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    Solid Waste Management Program Written Program Cornell University 8/28/2012 #12;Solid Waste.................................................................... 4 4.2.1 Compost Solid Waste Treatment Facility.................................................................... 4 4.2.2 Pathological Solid Waste Treatment Facility

  11. Proceedings of the tenth annual DOE low-level waste management conference: Session 4: Waste treatment minimization

    SciTech Connect (OSTI)

    Not Available

    1988-12-01T23:59:59.000Z

    This document contains eleven papers on various aspects of low-level radioactive waste management. Topics in this volume include: volume reduction plans; incentitives; and cost proposals; acid detoxification and reclamation; decontamination of lead; leach tests; West Valley demonstration project status report; and DOE's regional management strategies. Individual papers were processed separately for the data base. (TEM)

  12. The mutagenic potential of soil and runoff water from land treatment of three hazardous industrial wastes 

    E-Print Network [OSTI]

    Davol, Phebe

    1987-01-01T23:59:59.000Z

    (EPA, 1983). Land tr eatment may be a viable disposal alternative for many petroleum based hazardous wastes. This technology involves the controlled incorporation of wastes into the surface layer of soil resulting in degradation, immobilization... increased as the waste degraded, but began to decrease by the end of the study. Although the mechanism to explain this phenomena is unknown, it is possible that non-mutagenic compounds in the waste may have degraded into mutagenic compounds...

  13. Contaminant monitoring of biota downstream of a radioactive liquid waste treatment facility, Los Alamos National Laboratory

    SciTech Connect (OSTI)

    Bennett, K.D.; Biggs, J.R.; Fresquez, P.R. [Los Alamos National Lab., NM (United States). Environment, Safety, and Health Div.

    1996-12-31T23:59:59.000Z

    Small mammals, plants, and sediments were sampled at one upstream location (Site 1) and two downstream locations (Site 2 and Site 3) from the National Pollution Discharge Elimination System (NPDES) outfall {number_sign}051-051 in Mortandad Canyon, Los Alamos National Laboratory, Los Alamos, New Mexico. The purpose of the sampling was to identify radionuclides potentially present, to quantitatively estimate and compare the amount of radionuclide uptake at specific locations (Site 2 and Site 3) within Mortandad Canyon to an upstream site (Site 1), and to identify the primary mode (inhalation/ingestion or surface contact) of contamination to small mammals. Three composite samples of at least five animals per sample were collected at each site. The pelt was separated from the carcass of each animal and both were analyzed independently. In addition, three composite samples were also collected for plants and sediments at each site. Samples were analyzed for americium ({sup 241}Am), strontium ({sup 90}Sr), plutonium ({sup 238}Pu and {sup 239}Pu), and total uranium (U). With the exception of total U, all mean radionuclide concentrations in small mammal carcasses and sediments were significantly higher at Site 2 than Site 1 or Site 3. No differences were detected in the mean radionuclide concentration of plant samples between sites. However, some radionuclide concentrations found at all three sites were higher than regional background. No differences were found between mean carcass radionuclide concentrations and mean pelt radionuclide concentrations, indicating that the two primary modes of contamination may be equally occurring.

  14. Title Flood Assessment at the Proposed Area 6 Liquid Waste Treatment System - DOE/NV Test

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNLMay 20102 Hour ofGeologic

  15. 183-H Basin Mixed Waste Analysis and Testing Report

    SciTech Connect (OSTI)

    NONE

    1995-04-01T23:59:59.000Z

    The purpose of this sampling and analysis report is to provide data necessary to support treatment and disposal options for the low-level mixed waste from the 183-H solar evaporation ponds. In 1973, four of the 16 flocculation and sedimentation basins were designated for use as solar evaporation basins to provide waste reduction by natural evaporation of liquid chemical wastes from the 300 Area fuel fabrication facilities. The primary purpose of this effort is to gather chemical and bulk property data for the waste in the drums/boxes of sediment removed from the basin at Central Waste Complex.

  16. Implementation plan for liquid low-level radioactive waste systems under the FFA for fiscal years 1996 and 1997 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    NONE

    1996-06-01T23:59:59.000Z

    This document is the fourth annual revision of the plans and schedules for implementing the Federal Facility Agreement (FFA) compliance program, originally submitted in 1992 as ES/ER-17&D1, Federal Facility Agreement Plans and Schedules for Liquid Low-Level Radioactive Waste Tank Systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee. This document summarizes the progress that has been made to date implementing the plans and schedules for meeting the FFA commitments for the Liquid Low-Level Waste (LLLW) System at Oak Ridge National Laboratory (ORNL). In addition, this document lists FFA activities planned for FY 1997. Information presented in this document provides a comprehensive summary to facilitate understanding of the FFA compliance program for LLLW tank systems and to present plans and schedules associated with remediation, through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) process, of LLLW tank systems that have been removed from service.

  17. Analysis of the technical capabilities of DOE sites for disposal of residuals from the treatment of mixed low-level waste

    SciTech Connect (OSTI)

    Waters, R.D.; Gruebel, M.M.; Langkopf, B.S.; Kuehne, P.B.

    1997-04-01T23:59:59.000Z

    The US Department of Energy (DOE) has stored or expects to generate over the next five years more than 130,000 m{sup 3} of mixed low-level waste (MLLW). Before disposal, MLLW is usually treated to comply with the land disposal restrictions of the Resource Conservation and Recovery Act. Depending on the type of treatment, the original volume of MLLW and the radionuclide concentrations in the waste streams may change. These changes must be taken into account in determining the necessary disposal capacity at a site. Treatment may remove the characteristic in some waste that caused it to be classified as mixed. Treatment of some waste may, by reduction of the mass, increase the concentrations of some transuranic radionuclides sufficiently so that it becomes transuranic waste. In this report, the DOE MLLW streams were analyzed to determine after-treatment volumes and radionuclide concentrations. The waste streams were reclassified as residual MLLW or low-level or transuranic waste resulting from treatment. The volume analysis indicated that about 89,000 m{sup 3} of waste will require disposal as residual MLLW. Fifteen DOE sites were then evaluated to determine their capabilities for hosting disposal facilities for some or all of the residual MLLW. Waste streams associated with about 90% of the total residual MLLW volume are likely to present no significant issues for disposal and require little additional analysis. Future studies should focus on the remaining waste streams that are potentially problematic by examining site-specific waste acceptance criteria, alternative treatment processes, alternative waste forms for disposal, and pending changes in regulatory requirements.

  18. RADIOACTIVE DEMONSTRATION OF FINAL MINERALIZED WASTE FORMS FOR HANFORD WASTE TREATMENT PLANT SECONDARY WASTE (WTP-SW) BY FLUIDIZED BED STEAM REFORMING (FBSR) USING THE BENCH SCALE REFORMER PLATFORM

    SciTech Connect (OSTI)

    Crawford, C.; Burket, P.; Cozzi, A.; Daniel, G.; Jantzen, C.; Missimer, D.

    2014-08-21T23:59:59.000Z

    The U.S. Department of Energy’s Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford’s tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as {sup 137}Cs, {sup 129}I, {sup 99}Tc, Cl, F, and SO{sub 4} that volatilize at the vitrification temperature of 1150°C in the absence of a continuous cold cap (that could minimize volatilization). The current waste disposal path for the WTP-SW is to process it through the Effluent Treatment Facility (ETF). Fluidized Bed Steam Reforming (FBSR) is being considered for immobilization of the ETF concentrate that would be generated by processing the WTP-SW. The focus of this current report is the WTP-SW. FBSR offers a moderate temperature (700-750°C) continuous method by which WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be as durable as LAW glass. Monolithing of the granular FBSR product is being investigated to prevent dispersion during transport or burial/storage, but is not necessary for performance. A Benchscale Steam Reformer (BSR) was designed and constructed at the SRNL to treat actual radioactive wastes to confirm the findings of the non-radioactive FBSR pilot scale tests and to qualify the waste form for applications at Hanford. BSR testing with WTP SW waste surrogates and associated analytical analyses and tests of granular products (GP) and monoliths began in the Fall of 2009, and then was continued from the Fall of 2010 through the Spring of 2011. Radioactive testing commenced in 2010 with a demonstration of Hanford’s WTP-SW where Savannah River Site (SRS) High Level Waste (HLW) secondary waste from the Defense Waste Processing Facility (DWPF) was shimmed with a mixture of {sup 125/129}I and {sup 99}Tc to chemically resemble WTP-SW. Prior to these radioactive feed tests, non-radioactive simulants were also processed. Ninety six grams of radioactive granular product were made for testing and comparison to the non-radioactive pilot scale tests. The same mineral phases were found in the radioactive and non-radioactive testing. The granular products (both simulant and radioactive) were tested and a subset of the granular material (both simulant and radioactive) were stabilized in a geopolymer matrix. Extensive testing and characterization of the granular and monolith material were made including the following: ? ASTM C1285 (Product Consistency Test) testing of granular and monolith; ? ASTM C1308 accelerated leach testing of the radioactive monolith; ? ASTM C192 compression testing of monoliths; and ? EPA Method 1311 Toxicity Characteristic Leaching Procedure (TCLP) testing. The significant findings of the testing completed on simulant and radioactive WTP-SW are given below: ? Data indicates {sup 99}Tc, Re, Cs, and I

  19. Measurement and Treatment of Nuisance Odors at Wastewater Treatment Plants

    E-Print Network [OSTI]

    Abraham, Samantha Margaret

    2014-01-01T23:59:59.000Z

    oil refineries, and waste treatment operations such as composting, sludgeoil refineries, and waste treatment operations such as composting, sludge

  20. Delisting petition for 300-M saltstone (treated F006 sludge) from the 300-M liquid effluent treatment facility

    SciTech Connect (OSTI)

    Not Available

    1989-04-04T23:59:59.000Z

    This petition seeks exclusion for stabilized and solidified sludge material generated by treatment of wastewater from the 300-M aluminum forming and metal finishing processes. The waste contains both hazardous and radioactive components and is classified as a mixed waste. The objective of this petition is to demonstrate that the stabilized sludge material (saltstone), when properly disposed, will not exceed the health-based standards for the hazardous constituents. This petition contains sampling and analytical data which justify the request for exclusion. The results show that when the data are applied to the EPA Vertical and Horizontal Spread (VHS) Model, health-based standards for all hazardous waste constituents will not be exceeded during worst case operating and environmental conditions. Disposal of the stabilized sludge material in concrete vaults will meet the requirements pertaining to Waste Management Activities for Groundwater Protection at the Savannah River Site in Aiken, S.C. Documents set forth performance objectives and disposal options for low-level radioactive waste disposal. Concrete vaults specified for disposal of 300-M saltstone (treated F006 sludge) assure that these performance objectives will be met.

  1. MINERALIZING, STEAM REFORMING TREATMENT OF HANFORD LOW-ACTIVITY WASTE (a.k.a. INEEL/EXT-05-02526)

    SciTech Connect (OSTI)

    A. L. Olson; N. R. Soelberg; D. W. Marshall; G. L. Anderson

    2005-02-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) documented, in 2002, a plan for accelerating cleanup of the Hanford Site, located in southeastern Washington State, by at least 35 years. A key element of the plan was acceleration of the tank waste program and completion of ''tank waste treatment by 2028 by increasing the capacity of the planned Waste Treatment Plant (WTP) and using supplemental technologies for waste treatment and immobilization.'' The plan identified steam reforming technology as a candidate for supplemental treatment of as much as 70% of the low-activity waste (LAW). Mineralizing steam reforming technology, offered by THOR Treatment Technologies, LLC would produce a denitrated, granular mineral waste form using a high-temperature fluidized bed process. A pilot scale demonstration of the technology was completed in a 15-cm-diameter reactor vessel. The pilot scale facility was equipped with a cyclone separator and heated sintered metal filters for particulate removal, a thermal oxidizer for reduced gas species and NOx destruction, and a packed activated carbon bed for residual volatile species capture. The pilot scale equipment is owned by the DOE, but located at the Science and Technology Applications Research (STAR) Center in Idaho Falls, ID. Pilot scale testing was performed August 2–5, 2004. Flowsheet chemistry and operational parameters were defined through a collaborative effort involving Idaho National Engineering and Environmental Laboratory (INEEL), Savannah River National Laboratory (SRNL), and THOR Treatment Technologies personnel. Science Application International Corporation, owners of the STAR Center, personnel performed actual pilot scale operation. The pilot scale test achieved a total of 68.4 hours of cumulative/continuous processing operation before termination in response to a bed de-fluidization condition. 178 kg of LAW surrogate were processed that resulted in 148 kg of solid product, a mass reduction of about 17%. The process achieved essentially complete bed turnover within approximately 40 hours. Samples of mineralized solid product materials were analyzed for chemical/physical properties. SRNL will report separately the results of product performance testing that were accomplished.

  2. Ceramicrete stabilization of radioactive-salt-containing liquid waste and sludge water. Final CRADA report.

    SciTech Connect (OSTI)

    Ehst, D.; Nuclear Engineering Division

    2010-08-04T23:59:59.000Z

    It was found that the Ceramicrete Specimens incorporated the Streams 1 and 2 sludges with the adjusted loading about 41.6 and 31.6%, respectively, have a high solidity. The visible cracks in the matrix materials and around the anionite AV-17 granules included could not obtain. The granules mentioned above fixed by Ceramicrete matrix very strongly. Consequently, we can conclude that irradiation of Ceramecrete matrix, goes from the high radioactive elements, not result the structural degradation. Based on the chemical analysis of specimens No.462 and No.461 used it was shown that these matrix included the formation elements (P, K, Mg, O), but in the different samples their correlations are different. These ratios of the content of elements included are about {+-} 10%. This information shows a great homogeneity of matrix prepared. In the list of the elements founded, expect the matrix formation elements, we detected also Ca and Si (from the wollastonite - the necessary for Ceramicrete compound); Na, Al, S, O, Cl, Fe, Ni also have been detected in the Specimen No.642 from the waste forms: NaCl, Al(OH){sub 3}, Na{sub 2}SO{sub 4}. Fe(OH){sub 3}, nickel ferrocyanide and Ni(NO{sub 3})2. The unintelligible results also were found from analysis of an AV-17 granules, in which we obtain the great amount of K. The X-ray radiographs of the Ceramicrete specimens with loading 41.4 % of Stream 1 and 31.6% of Stream 2, respectively showed that the realization of the advance technology, created at GEOHKI, leads to formation of excellent ceramic matrix with high amount of radioactive streams up to 40% and more. Really, during the interaction with start compounds MgO and KH{sub 2}PO{sub 4} with the present of H{sub 3}BO{sub 3} and Wollastonite this process run with high speed under the controlled regimes. That fact that the Ceramicrete matrix with 30-40% of Streams 1 and 2 have a crystalline form, not amorphous matter, allows to permit that these matrix should be very stable, reliable for incorporation of a radionuclides.

  3. Numerical simulation of hydrothermal salt separation process and analysis and cost estimating of shipboard liquid waste disposal

    E-Print Network [OSTI]

    Hunt, Andrew Robert

    2007-01-01T23:59:59.000Z

    Due to environmental regulations, waste water disposal for US Navy ships has become a requirement which impacts both operations and the US Navy's budget. In 2006, the cost for waste water disposal Navy-wide was 54 million ...

  4. Laboratory Report on Performance Evaluation of Key Constituents during Pre-Treatment of High Level Waste Direct Feed

    SciTech Connect (OSTI)

    Huber, Heinz J.

    2013-06-24T23:59:59.000Z

    The analytical capabilities of the 222-S Laboratory are tested against the requirements for an optional start up scenario of the Waste Treatment and Immobilization Plant on the Hanford Site. In this case, washed and in-tank leached sludge would be sent directly to the High Level Melter, bypassing Pretreatment. The sludge samples would need to be analyzed for certain key constituents in terms identifying melter-related issues and adjustment needs. The analyses on original tank waste as well as on washed and leached material were performed using five sludge samples from tanks 241-AY-102, 241-AZ-102, 241-AN-106, 241-AW-105, and 241-SY-102. Additionally, solid phase characterization was applied to determine the changes in mineralogy throughout the pre-treatment steps.

  5. Influence of mechanical-biological waste pre-treatment methods on the gas formation in landfills

    SciTech Connect (OSTI)

    Bockreis, A. [Technische Universitaet Darmstadt, Darmstadt University of Technology, Institute for Water Supply and Groundwater Protection, Wastewater Technology, Waste Management, Industrial Material Flows and Environmental Planning (Institute WAR), Chair of Waste Management and Waste Technology, Darmstadt (Germany)]. E-mail: a.bockreis@iwar.tu-darmstadt.de; Steinberg, I. [Technische Universitaet Darmstadt, Darmstadt University of Technology, Institute for Water Supply and Groundwater Protection, Wastewater Technology, Waste Management, Industrial Material Flows and Environmental Planning (Institute WAR), Chair of Waste Management and Waste Technology, Darmstadt (Germany)

    2005-07-01T23:59:59.000Z

    In order to minimise emissions and environmental impacts, only pre-treated waste should be disposed of. For the last six years, a series of continuous experiments has been conducted at the Institute WAR, TU Darmstadt, in order to determine the emissions from pre-treated waste. Different kinds of pre-treated waste were incubated in several reactors and various data, including production and composition of the gas and the leachate, were collected. In this paper, the interim results of gas production and the gas composition from different types of waste after a running time of six years are presented and discussed.

  6. Vitrification as a low-level radioactive mixed waste treatment technology at Argonne National Laboratory

    SciTech Connect (OSTI)

    Mazer, J.J.; No, Hyo J.

    1995-08-01T23:59:59.000Z

    Argonne National Laboratory-East (ANL-E) is developing plans to use vitrification to treat low-level radioactive mixed wastes (LLMW) generated onsite. The ultimate objective of this project is to install a full-scale vitrification system at ANL-E capable of processing the annual generation and historic stockpiles of selected LLMW streams. This project is currently in the process of identifying a range of processible glass compositions that can be produced from actual mixed wastes and additives, such as boric acid or borax. During the formulation of these glasses, there has been an emphasis on maximizing the waste content in the glass (70 to 90 wt %), reducing the overall final waste volume, and producing a stabilized low-level radioactive waste glass. Crucible glass studies with actual mixed waste streams have produced alkali borosilicate glasses that pass the Toxic Characteristic Leaching Procedure (TCLP) test. These same glass compositions, spiked with toxic metals well above the expected levels in actual wastes, also pass the TCLP test. These results provide compelling evidence that the vitrification system and the glass waste form will be robust enough to accommodate expected variations in the LLMW streams from ANL-E. Approximately 40 crucible melts will be studied to establish a compositional envelope for vitrifying ANL-E mixed wastes. Also being determined is the identity of volatilized metals or off-gases that will be generated.

  7. Implementation Plan for Liquid Low-Level Radioactive Waste tank systems at Oak Ridge National Laboratory under the Federal Facility Agreement, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    This document summarizes the progress that has been made to date in implementing the plans and schedules for meeting the Federal Facility Agreement (FFA) commitments for the Liquid Low-Level Waste (LLLW) System at Oak Ridge National Laboratory (ORNL). These commitments were initially submitted in ES/ER-17&Dl, Federal Facility Agreement Plans and Schedules for Liquid Low-Level Radioactive Waste Tank Systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Information presented in this document provides a comprehensive summary to facilitate understanding of the FFA compliance program for LLLW tank systems and to present plans and schedules associated with remediation, through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) process, of LLLW tank systems that have been removed from service. ORNL has a comprehensive program underway to upgrade the LLLW system as necessary to meet the FFA requirements. The tank systems that are removed from service are being investigated and remediated through the CERCLA process. Waste and risk characterizations have been submitted. Additional data will be prepared and submitted to EPA/TDEC as tanks are taken out of service and as required by the remedial investigation/feasibility study (RI/FS) process. The plans and schedules for implementing the FFA compliance program that were submitted in ES/ER-17&Dl, Federal Facility Agreement Plans and Schedules for Liquid Low-Level Radioactive Waste tanks Systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee, are updated in this document. Chapter 1 provides general background information and philosophies that lead to the plans and schedules that appear in Chaps. 2 through 5.

  8. Improved Management of the Technical Interfaces Between the Hanford Tank Farm Operator and the Hanford Waste Treatment Plant - 13383

    SciTech Connect (OSTI)

    Duncan, Garth M. [Bechtel National Inc., 2435 Stevens Center Place, Richland, Washington, 99352 (United States)] [Bechtel National Inc., 2435 Stevens Center Place, Richland, Washington, 99352 (United States); Saunders, Scott A. [Washington River Protection Solutions, P.O. Box 850, Richland, Washington, 99352 (United States)] [Washington River Protection Solutions, P.O. Box 850, Richland, Washington, 99352 (United States)

    2013-07-01T23:59:59.000Z

    The Department of Energy (DOE) is constructing the Waste Treatment and Immobilization Plant (WTP) at the Hanford site in Washington to treat and immobilize approximately 114 million gallons of high level radioactive waste (after all retrievals are accomplished). In order for the WTP to be designed and operated successfully, close coordination between the WTP engineering, procurement, and construction contractor, Bechtel National, Inc. and the tank farms operating contractor (TOC), Washington River Protection Solutions, LLC, is necessary. To develop optimal solutions for DOE and for the treatment of the waste, it is important to deal with the fact that two different prime contractors, with somewhat differing contracts, are tasked with retrieving and delivering the waste and for treating and immobilizing that waste. The WTP and the TOC have over the years cooperated to manage the technical interface. To manage what is becoming a much more complicated interface as the WTP design progresses and new technical issues have been identified, an organizational change was made by WTP and TOC in November of 2011. This organizational change created a co-located integrated project team (IPT) to deal with mutual and interface issues. The Technical Organization within the One System IPT includes employees from both TOC and WTP. This team has worked on a variety of technical issues of mutual interest and concern. Technical issues currently being addressed include: - The waste acceptance criteria; - Waste feed delivery and the associated data quality objectives (DQO); - Evaluation of the effects of performing a riser cut on a single shell tank on WTP operations; - The disposition of secondary waste from both TOC and WTP; - The close coordination of the TOC double shell tank mixing and sampling program and the Large Scale Integrated Test (LSIT) program for pulse jet mixers at WTP along with the associated responses to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2010-2; - Development of a set of alternatives to the current baseline that involve aspects of direct feed, feed conditioning, and design changes. The One System Technical Organization has served WTP, TOC, and DOE well in managing and resolving issues at the interface. This paper describes the organizational structure used to improve the interface and several examples of technical interface issues that have been successfully addressed by the new organization. (authors)

  9. EIS-0356: Retrieval, Treatment and Disposal of Tank Wastes and Closure of Single-Shell Tanks at the Hanford Site, Richland, WA

    Broader source: Energy.gov [DOE]

    This EIS analyzes DOE's proposed retrieval, treatment, and disposal of the waste being managed in the high-level waste (HLW) tank farms at the Hanford Site near Richland, Washington, and closure of the 149 single-shell tanks (SSTs) and associated facilities in the HLW tank farms.

  10. FLUIDIZED BED STEAM REFORMING FOR TREATMENT AND IMMOBILIZATION OF LOW-ACTIVITY WASTE

    SciTech Connect (OSTI)

    HEWITT WM

    2011-04-08T23:59:59.000Z

    This report is one of four reports written to provide background information regarding immobilization technologies remaining under consideration for supplemental immobilization of Hanford's low-activity waste. This paper provides the reader a general understanding of fluidized bed steam reforming and its possible application to treat and immobilize Hanford low-activity waste.

  11. A JOULE-HEATED MELTER TECHNOLOGY FOR THE TREATMENT AND IMMOBILIZATION OF LOW-ACTIVITY WASTE

    SciTech Connect (OSTI)

    KELLY SE

    2011-04-07T23:59:59.000Z

    This report is one of four reports written to provide background information regarding immobilization technologies remaining under consideration for supplemental immobilization of Hanford's low-activity waste. This paper provides the reader a general understanding of joule-heated ceramic lined melters and their application to Hanford's low-activity waste.

  12. BULK VITRIFICATION TECHNOLOGY FOR THE TREATMENT AND IMMOBILIZATION OF LOW-ACTIVITY WASTE

    SciTech Connect (OSTI)

    ARD KE

    2011-04-11T23:59:59.000Z

    This report is one of four reports written to provide background information regarding immobilization technologies under consideration for supplemental immobilization of Hanford's low-activity waste. This paper is intended to provide the reader with general understanding of Bulk Vitrification and how it might be applied to immobilization of Hanford's low-activity waste.

  13. SARDINIA2003_2_Infrastructure.doc 1 Waste Treatment Infrastructure in North Rhine-Westphalia,

    E-Print Network [OSTI]

    Columbia University

    % of German hazardous waste. These conditions led to an extreme variety of disposal and recycling activities management boards. This waste disposal and recycling register has been existing and growing in number 3090 recycling and disposal plants in operation (Appendix 1, status June 2000). The disposal

  14. Anaerobic co-digestion of the organic fraction of municipal solid waste with FOG waste from a sewage treatment plant: Recovering a wasted methane potential and enhancing the biogas yield

    SciTech Connect (OSTI)

    Martin-Gonzalez, L., E-mail: lucia.martin@uab.ca [Departament d'Enginyeria Quimica, Universitat Autonoma de Barcelona, 08193 Bellaterra (Spain); Colturato, L.F. [Departament d'Enginyeria Quimica, Universitat Autonoma de Barcelona, 08193 Bellaterra (Spain); Font, X.; Vicent, T. [Departament d'Enginyeria Quimica, Universitat Autonoma de Barcelona, 08193 Bellaterra (Spain); Institut de Ciencia i Tecnologia Ambiental (ICTA) Universitat Autonoma de Barcelona, 08193 Bellaterra (Spain)

    2010-10-15T23:59:59.000Z

    Anaerobic digestion is applied widely to treat the source collected organic fraction of municipal solid wastes (SC-OFMSW). Lipid-rich wastes are a valuable substrate for anaerobic digestion due to their high theoretical methane potential. Nevertheless, although fat, oil and grease waste from sewage treatment plants (STP-FOGW) are commonly disposed of in landfill, European legislation is aimed at encouraging more effective forms of treatment. Co-digestion of the above wastes may enhance valorisation of STP-FOGW and lead to a higher biogas yield throughout the anaerobic digestion process. In the present study, STP-FOGW was evaluated as a co-substrate in wet anaerobic digestion of SC-OFMSW under mesophilic conditions (37 {sup o}C). Batch experiments carried out at different co-digestion ratios showed an improvement in methane production related to STP-FOGW addition. A 1:7 (VS/VS) STP-FOGW:SC-OFMSW feed ratio was selected for use in performing further lab-scale studies in a 5 L continuous reactor. Biogas yield increased from 0.38 {+-} 0.02 L g VS{sub feed}{sup -1} to 0.55 {+-} 0.05 L g VS{sub feed}{sup -1} as a result of adding STP-FOGW to reactor feed. Both VS reduction values and biogas methane content were maintained and inhibition produced by long chain fatty acid (LCFA) accumulation was not observed. Recovery of a currently wasted methane potential from STP-FOGW was achieved in a co-digestion process with SC-OFMSW.

  15. Updated Site Response Analyses for the Waste Treatment Plant, DOE Hanford, Site, Washington.

    SciTech Connect (OSTI)

    Youngs, Robert R.

    2007-06-29T23:59:59.000Z

    This document describes the calculations performed to develop updated relative amplification functions for the Waste Treatment and Immobilization Plant (WTP) facility at the DOE Hanford Site, Washington State. The original 2,000-year return period design spectra for the WTP were based on the results of a probabilistic seismic hazard analysis (PSHA) performed for the DOE Hanford Site by Geomatrix (1996). Geomatrix (1996) performed the PSHA using empirical soil-site ground motion models based primarily on recordings from California. As part of that study, site response analyses were performed to evaluate ground motions at the Hanford sites and California deep soil sites. As described in Appendix A of Geomatrix (1996), characteristic site profiles and dynamic soil properties representative of conditions at various Hanford sites and California deep soil strong motion recording stations were defined. Relative site responses of the Hanford profiles and California profiles were then compared. Based on the results of those site response analyses, it was concluded that ground motions at the Hanford sites underlain by deep soil deposits are similar in character to those on California deep soil sites and it was judged appropriate to use empirical deep soil site attenuation relationships based primarily on California ground motion data to develop design spectra for the Hanford sites. In a subsequent analysis, Geomatrix (2003) updated the site response analyses of Geomatrix (1996, Appendix A) to incorporate randomization of the California and Hanford profiles. The results of that analysis also led to the conclusion that the response of the Hanford profiles was similar to the response of deep soil sites in California.

  16. Combined heat treatment and acid hydrolysis of cassava grate waste (CGW) biomass for ethanol production

    SciTech Connect (OSTI)

    Agu, R.C.; Amadife, A.E.; Ude, C.M.; Onyia, A.; Ogu, E.O. [Enugu State Univ. of Science and Technology (Nigeria). Faculty of Applied Natural Sciences] [Enugu State Univ. of Science and Technology (Nigeria). Faculty of Applied Natural Sciences; Okafor, M.; Ezejiofor, E. [Nnamdi Azikiwe Univ., Awka (Nigeria). Dept. of Applied Microbiology] [Nnamdi Azikiwe Univ., Awka (Nigeria). Dept. of Applied Microbiology

    1997-12-31T23:59:59.000Z

    The effect of combined heat treatment and acid hydrolysis (various concentrations) on cassava grate waste (CGW) biomass for ethanol production was investigated. At high concentrations of H{sub 2}SO{sub 4} (1--5 M), hydrolysis of the CGW biomass was achieved but with excessive charring or dehydration reaction. At lower acid concentrations, hydrolysis of CGW biomass was also achieved with 0.3--0.5 M H{sub 2}SO{sub 4}, while partial hydrolysis was obtained below 0.3 M H{sub 2}SO{sub 4} (the lowest acid concentration that hydrolyzed CGW biomass) at 120 C and 1 atm pressure for 30 min. A 60% process efficiency was achieved with 0.3 M H{sub 2}SO{sub 4} in hydrolyzing the cellulose and lignin materials present in the CGW biomass. High acid concentration is therefore not required for CGW biomass hydrolysis. The low acid concentration required for CGW biomass hydrolysis, as well as the minimal cost required for detoxification of CGW biomass because of low hydrogen cyanide content of CGW biomass would seem to make this process very economical. From three liters of the CGW biomass hydrolysate obtained from hydrolysis with 0.3M H{sub 2}SO{sub 4}, ethanol yield was 3.5 (v/v%) after yeast fermentation. However, although the process resulted in gainful utilization of CGW biomass, additional costs would be required to effectively dispose new by-products generated from CGW biomass processing.

  17. Dismantlement and Radioactive Waste Management of DPRK Nuclear Facilities

    SciTech Connect (OSTI)

    Jooho, W.; Baldwin, G. T.

    2005-04-01T23:59:59.000Z

    One critical aspect of any denuclearization of the Democratic People’s Republic of Korea (DPRK) involves dismantlement of its nuclear facilities and management of their associated radioactive wastes. The decommissioning problem for its two principal operational plutonium facilities at Yongbyun, the 5MWe nuclear reactor and the Radiochemical Laboratory reprocessing facility, alone present a formidable challenge. Dismantling those facilities will create radioactive waste in addition to existing inventories of spent fuel and reprocessing wastes. Negotiations with the DPRK, such as the Six Party Talks, need to appreciate the enormous scale of the radioactive waste management problem resulting from dismantlement. The two operating plutonium facilities, along with their legacy wastes, will result in anywhere from 50 to 100 metric tons of uranium spent fuel, as much as 500,000 liters of liquid high-level waste, as well as miscellaneous high-level waste sources from the Radiochemical Laboratory. A substantial quantity of intermediate-level waste will result from disposing 600 metric tons of graphite from the reactor, an undetermined quantity of chemical decladding liquid waste from reprocessing, and hundreds of tons of contaminated concrete and metal from facility dismantlement. Various facilities for dismantlement, decontamination, waste treatment and packaging, and storage will be needed. The shipment of spent fuel and liquid high level waste out of the DPRK is also likely to be required. Nuclear facility dismantlement and radioactive waste management in the DPRK are all the more difficult because of nuclear nonproliferation constraints, including the call by the United States for “complete, verifiable and irreversible dismantlement,” or “CVID.” It is desirable to accomplish dismantlement quickly, but many aspects of the radioactive waste management cannot be achieved without careful assessment, planning and preparation, sustained commitment, and long completion times. The radioactive waste management problem in fact offers a prospect for international participation to engage the DPRK constructively. DPRK nuclear dismantlement, when accompanied with a concerted effort for effective radioactive waste management, can be a mutually beneficial goal.

  18. Hanford Waste Physical and Rheological Properties: Data and Gaps

    SciTech Connect (OSTI)

    Wells, Beric E.; Kurath, Dean E.; Mahoney, Lenna A.; Onishi, Yasuo; Huckaby, James L.; Cooley, Scott K.; Burns, Carolyn A.; Buck, Edgar C.; Tingey, Joel M.; Daniel, Richard C.; Anderson, K. K.

    2011-08-01T23:59:59.000Z

    The Hanford Site in Washington State manages 177 underground storage tanks containing approximately 250,000 m3 of waste generated during past defense reprocessing and waste management operations. These tanks contain a mixture of sludge, saltcake and supernatant liquids. The insoluble sludge fraction of the waste consists of metal oxides and hydroxides and contains the bulk of many radionuclides such as the transuranic components and 90Sr. The saltcake, generated by extensive evaporation of aqueous solutions, consists primarily of dried sodium salts. The supernates consist of concentrated (5-15 M) aqueous solutions of sodium and potassium salts. The 177 storage tanks include 149 single-shell tanks (SSTs) and 28 double -hell tanks (DSTs). Ultimately the wastes need to be retrieved from the tanks for treatment and disposal. The SSTs contain minimal amounts of liquid wastes, and the Tank Operations Contractor is continuing a program of moving solid wastes from SSTs to interim storage in the DSTs. The Hanford DST system provides the staging location for waste feed delivery to the Department of Energy (DOE) Office of River Protection’s (ORP) Hanford Tank Waste Treatment and Immobilization Plant (WTP). The WTP is being designed and constructed to pretreat and then vitrify a large portion of the wastes in Hanford’s 177 underground waste storage tanks.

  19. Structural Integrity Program for the 300,000-Gallon Radioactive Liquid Waste Storage Tanks at the Idaho Nuclear Technology and Engineering Center

    SciTech Connect (OSTI)

    Bryant, Jeffrey W.

    2010-08-12T23:59:59.000Z

    This report provides a record of the Structural Integrity Program for the 300,000-gal liquid waste storage tanks and associated equipment at the Idaho Nuclear Technology and Engineering Center, as required by U.S. Department of Energy M 435.1-1, “Radioactive Waste Management Manual.” This equipment is known collectively as the Tank Farm Facility. This report is an update, and replaces the previous report by the same title issued April 2003. The conclusion of this report is that the Tank Farm Facility tanks, vaults, and transfer systems that remain in service for storage are structurally adequate, and are expected to remain structurally adequate over the remainder of their planned service life through 2012. Recommendations are provided for continued monitoring of the Tank Farm Facility.

  20. EA-1135: Offsite Thermal Treatment of Low-level Mixed Waste, Richland, Washington

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the proposal to treat contact-handled low-level mixed waste, containing polychlorinated biphenyls and other organics, to meet existing regulatory...

  1. PROGRAMMATIC ASSESSMENT OF RADIOACTIVE WASTE MANAGEMENT NUCLEAR FUEL AND WASTE PROGRAMS. Operational Planning and Development (Activity No. AR OS 10 05 K; ONL-WN06)

    SciTech Connect (OSTI)

    None

    1980-06-30T23:59:59.000Z

    Gilbert/Commonwealth (G/C) has performed an assessment of the waste management operations at Oak Ridge National Laboratory (ORNL). The objective of this study was to review radioactive waste management as practiced at ORNL and to recommend improvements or alternatives for further study. The study involved: 1) an on-site survey of ORNL radioactive waste management operations; 2) a review of radioactive waste source data, records, and regulatory requirements; 3) an assessment of existing and planned treatment, storage, and control facilities; and 4) identification of alternatives for improving waste management operations. Information for this study was obtained from both personal interviews and written reports. The G/C suggestions for improving ORNL waste management operations are summarized. Regulatory requirements governing ORNL waste management operations are discussed. Descriptions and discussions of the radioactive liquid, solid, and gaseous waste systems are presented. The waste operations control complex is discussed.

  2. Spent Fuel and Waste Management Technology Development Program. Annual progress report

    SciTech Connect (OSTI)

    Bryant, J.W.

    1994-01-01T23:59:59.000Z

    This report provides information on the progress of activities during fiscal year 1993 in the Spent Fuel and Waste Management Technology Development Program (SF&WMTDP) at the Idaho Chemical Processing Plant (ICPP). As a new program, efforts are just getting underway toward addressing major issues related to the fuel and waste stored at the ICPP. The SF&WMTDP has the following principal objectives: Investigate direct dispositioning of spent fuel, striving for one acceptable waste form; determine the best treatment process(es) for liquid and calcine wastes to minimize the volume of high level radioactive waste (HLW) and low level waste (LLW); demonstrate the integrated operability and maintainability of selected treatment and immobilization processes; and assure that implementation of the selected waste treatment process is environmentally acceptable, ensures public and worker safety, and is economically feasible.

  3. NOCHAR Polymers: An Aqueous and Organic Liquid Solidification Process for Cadarache LOR (Liquides Organiques Radioactifs) - 13195

    SciTech Connect (OSTI)

    Vaudey, Claire-Emilie; Renou, Sebastien; Porco, Julien [AREVA CL BU, STMI ZAC de Courcelle 1 route de la Noue 91196 Gif-sur-Yvette (France)] [AREVA CL BU, STMI ZAC de Courcelle 1 route de la Noue 91196 Gif-sur-Yvette (France); Kelley, Dennis [Pacific World Trade, Inc. Hillsdale Technical Center 6970 Hillsdale Court Indianapolis, Indiana 46250 (United States)] [Pacific World Trade, Inc. Hillsdale Technical Center 6970 Hillsdale Court Indianapolis, Indiana 46250 (United States); Cochaud, Chantal [CEA Cadarache, DSN/SGTD, 13108 St Paul Lez Durance Cedex (France)] [CEA Cadarache, DSN/SGTD, 13108 St Paul Lez Durance Cedex (France); Serrano, Roger [CEA Marcoule, DPAD, BP 17171, 30207 Bagnols sur Ceze Cedex (France)] [CEA Marcoule, DPAD, BP 17171, 30207 Bagnols sur Ceze Cedex (France)

    2013-07-01T23:59:59.000Z

    To handle the Very Low Level Waste (VLLW) and the Low Level Waste (LLW) in France, two options can be considered: the incineration at CENTRACO facility and the disposal facility on ANDRA sites. The waste acceptance in these radwaste routes is dependent upon the adequacy between the waste characteristics (physical chemistry and radiological) and the radwaste route specifications. If the waste characteristics are incompatible with the radwaste route specifications (presence of significant quantities of chlorine, fluorine, organic component etc or/and high activity limits), it is necessary to find an alternative solution that consists of a waste pre-treatment process. In the context of the problematic Cadarache LOR (Liquides Organiques Radioactifs) waste streams, two radioactive scintillation cocktails have to be treated. The first one is composed of organic liquids at 13.1 % (diphenyloxazol, mesitylene, TBP, xylene) and water at 86.9 %. The second one is composed of TBP at 8.6 % and water at 91.4 %. They contain chlorine, fluorine and sulphate and have got alpha/beta/gamma spectra with mass activities equal to some kBq.g{sup -1}. Therefore, tritium is present and creates the second problematic waste stream. As a consequence, in order for disposal acceptance at the ANDRA site, it is necessary to pre-treat the waste. The NOCHAR polymers as an aqueous and organic liquid solidification process seem to be an adequate solution. Indeed, these polymers constitute an important variety of products applied to the treatment of radioactive aqueous and organic liquids (solvent, oil, solvent/oil mixing etc) and sludge through a mechanical and chemical solidification process. For Cadarache LOR, N910 and N960 respectively dedicated to the organic and aqueous liquids solidification are considered. With the N910, the organic waste solidification occurs in two steps. As the organic liquid travels moves through the polymer strands, the strands swell and immobilise the liquid. Then as the polymer-organic cure, over time, the polymer continues to collapse on the organic to create a permanent bond. The N960 has the ability to absorb aqueous waste up to 100 times its own weight. It creates a strong mechanical bond which permanently traps the contamination imbedded in the aqueous liquids. As a consequence, these two polymers seem to be able to constitute a suitable solidification matrix for a final acceptance in storage on ANDRA sites. In order to validate the polymers as an acceptable aqueous and organic solidification process for Cadarache LOR, some solidification tests realized with N910 and N960, have been carried out for different Waste/Polymer ratios. The determination of the best Waste/Polymer ratio and of the optimal experimental parameters has been made through an exudation test. Indeed, the process prevents leaching and it results in the absence of residual free organic or aqueous liquid which is forbidden in storage by ANDRA specifications. With these test results, we generated scientific data which are fundamental to obtain an ANDRA agreement. As a conclusion, the aim of this study is to demonstrate that the solidification by polymers can constitute a pre-treatment solution for Cadarache LOR and more generally, for various organic and mixed organic/aqueous waste which can not be directly acceptable at CENTRACO facility or at ANDRA storage sites. This work is, therefore, a solid background to demonstrate the feasibility of the waste pre-treatment by solidification with polymers and to encourage the development of this process. (authors)

  4. In Situ Grouting of Liquid Waste Disposal Trenches and Experimental Reactor Fuel Disposal Wells at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Johnson, Ch.; Cange, J.; Lambert, R. [Bechtel Jacobs Company, LLC, Oak Ridge, TN (United States); Trujillo, E. [BWXT Pantex, LLC, Amarillo, TX (United States); Julius, J. [U.S. DOE, Oak Ridge Operations Office, Oak Ridge, TN (United States)

    2008-07-01T23:59:59.000Z

    In the early to mid-1960's, liquid low-level wastes (LLLW) generated at Oak Ridge National Laboratory were disposed of in specially-constructed, gravel-filled trenches within the Melton Valley watershed at the lab. The initial selected remedy for Trenches 5 and 7 was in situ vitrification; however, an amendment to the record of decision changed the remedy to in situ grouting of the trenches. The work was accomplished by filling the void space within the crushed stone section of each trench with cementitious grout. The contaminated soil surrounding the trenches (1-m perimeter) was then grouted with acrylamide grout. At the HRE fuel wells, a 1-m ring of soil surrounding the fuel wells was grouted with acrylamide. The results of the hydraulic conductivity tests ranged from 4.74 x 10{sup -6} to 3.60 x 10{sup -7} cm/sec, values that were well below the 1 x 10{sup -5} cm/sec design criterion. In summary: The ISG Project was conducted to decrease hydraulic conductivity and thereby decrease water flow and contaminate migration from the area of the trenches. The initial remedy for Trenches 5 and 7 in the Melton Valley ROD was for in situ vitrification of the trench matrix. The remedy was changed to in situ grouting of the trenches and HRE fuel wells through an amendment to the ROD after moisture was found in the trenches. The grouting of the trenches was accomplished by filling the void space within the crushed stone section of each trench with cementitious grout. The contaminated soil surrounding the trenches (1-m perimeter) was then grouted with acrylamide grout to further reduce water infiltration. Soil backfill above each of the seven HRE fuel wells was removed to a depth of approximately 1 m by augering, and the soils were replaced with a cement plug to prevent water infiltration from migrating down the original borehole. Soil surrounding the fuel wells was then grouted with acrylamide to ensure water infiltration through the HRE fuel wells is prevented. A summary of the quantities used is shown. After completion of grouting, in-situ hydraulic conductivities of the grouted materials were measured to verify attainment of the design objective. The areas were then covered with multi-layer caps as part of the MV hydrologic isolation project. (authors)

  5. Secondary Waste Form Screening Test Results—THOR® Fluidized Bed Steam Reforming Product in a Geopolymer Matrix

    SciTech Connect (OSTI)

    Pires, Richard P.; Westsik, Joseph H.; Serne, R. Jeffrey; Mattigod, Shas V.; Golovich, Elizabeth C.; Valenta, Michelle M.; Parker, Kent E.

    2011-07-14T23:59:59.000Z

    Screening tests are being conducted to evaluate waste forms for immobilizing secondary liquid wastes from the Hanford Tank Waste Treatment and Immobilization Plant (WTP). Plans are underway to add a stabilization treatment unit to the Effluent Treatment Facility to provide the needed capacity for treating these wastes from WTP. The current baseline is to use a Cast Stone cementitious waste form to solidify the wastes. Through a literature survey, DuraLith alkali-aluminosilicate geopolymer, fluidized-bed steam reformation (FBSR) granular product encapsulated in a geopolymer matrix, and a Ceramicrete phosphate-bonded ceramic were identified both as candidate waste forms and alternatives to the baseline. These waste forms have been shown to meet waste disposal acceptance criteria, including compressive strength and universal treatment standards for Resource Conservation and Recovery Act (RCRA) metals (as measured by the toxicity characteristic leaching procedure [TCLP]). Thus, these non-cementitious waste forms should also be acceptable for land disposal. Information is needed on all four waste forms with respect to their capability to minimize the release of technetium. Technetium is a radionuclide predicted to be in the secondary liquid wastes in small quantities, but the Integrated Disposal Facility (IDF) risk assessment analyses show that technetium, even at low mass, produces the largest contribution to the estimated IDF disposal impacts to groundwater.

  6. SCFA lead lab technical assistance at Oak Ridge Y-12 national security complex: Evaluation of treatment and characterization alternatives of mixed waste soil and debris at disposal area remedial action DARA solids storage facility (SSF)

    E-Print Network [OSTI]

    Hazen, Terry

    2002-01-01T23:59:59.000Z

    TREATMENT AND CHARACTERIZATION ALTERNATIVES OF MIXED WASTE SOIL AND DEBRIS AT DISPOSAL AREA REMEDIAL ACTION (DARA) SOLIDSTreatment and Characterization Alternatives for Mixed Waste Soil and Debris at Disposal Area Remedial Action (DARA) Solids

  7. Final Environmental Impact Statement for Treating Transuranic (TRU)/Alpha Low-level Waste at the Oak Ridge National Laboratory Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    N /A

    2000-06-30T23:59:59.000Z

    The DOE proposes to construct, operate, and decontaminate/decommission a TRU Waste Treatment Facility in Oak Ridge, Tennessee. The four waste types that would be treated at the proposed facility would be remote-handled TRU mixed waste sludge, liquid low-level waste associated with the sludge, contact-handled TRU/alpha low-level waste solids, and remote-handled TRU/alpha low-level waste solids. The mixed waste sludge and some of the solid waste contain metals regulated under the Resource Conservation and Recovery Act and may be classified as mixed waste. This document analyzes the potential environmental impacts associated with five alternatives--No Action, the Low-Temperature Drying Alternative (Preferred Alternative), the Vitrification Alternative, the Cementation Alternative, and the Treatment and Waste Storage at Oak Ridge National Laboratory (ORNL) Alternative.

  8. State Waste Discharge Permit application: 400 Area Septic System

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    As part of the Hanford Federal Facility Agreement and Consent Order negotiations, the US Department of Energy, Richland Operations Office, the US Environmental Protection Agency, and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground on the Hanford Site which affects groundwater or has the potential to affect groundwater would be subject to permitting under the structure of Chapter 173-216 (or 173-218 where applicable) of the Washington Administrative Code, the State Waste Discharge Permit Program. This document constitutes the State Waste Discharge Permit application for the 400 Area Septic System. The influent to the system is domestic waste water. Although the 400 Area Septic System is not a Public Owned Treatment Works, the Public Owned Treatment Works application is more applicable than the application for industrial waste water. Therefore, the State Waste Discharge Permit application for Public Owned Treatment Works Discharges to Land was used.

  9. Aqueous nitrate waste treatment: Technology comparison, cost/benefit, and market analysis

    SciTech Connect (OSTI)

    Not Available

    1994-01-01T23:59:59.000Z

    The purpose of this analysis is to provide information necessary for the Department of Energy (DOE) to evaluate the practical utility of the Nitrate to Ammonia and Ceramic or Glass (NAC/NAG/NAX) process, which is under development in the Oak Ridge National Laboratory. The NAC/NACx/NAX process can convert aqueous radioactive nitrate-laden waste to a glass, ceramic, or grout solid waste form. The tasks include, but are not limited to, the following: Identify current commercial technologies to meet hazardous and radiological waste disposal requirements. The technologies may be thermal or non-thermal but must be all inclusive (i.e., must convert a radionuclide-containing nitrate waste with a pH around 12 to a stable form that can be disposed at permitted facilities); evaluate and compare DOE-sponsored vitrification, grouting, and minimum additive waste stabilization projects for life-cycle costs; compare the technologies above with respect to material costs, capital equipment costs, operating costs, and operating efficiencies. For the NAC/NAG/NAX process, assume aluminum reactant is government furnished and ammonia gas may be marketed; compare the identified technologies with respect to frequency of use within DOE for environmental management applications with appropriate rationale for use; Assess the potential size of the DOE market for the NAC/NAG/NAX process; assess and off-gas issues; and compare with international technologies, including life-cycle estimates.

  10. Summary Report of Geophysical Logging For The Seismic Boreholes Project at the Hanford Site Waste Treatment Plant.

    SciTech Connect (OSTI)

    Gardner, Martin G.; Price, Randall K.

    2007-02-01T23:59:59.000Z

    During the period of June through October 2006, three deep boreholes and one corehole were drilled beneath the site of the Waste Treatment Plant (WTP) at the U.S. Department of Energy (DOE) Hanford Site near Richland, Washington. The boreholes were drilled to provide information on ground-motion attenuation in the basalt and interbedded sediments underlying the WTP site. This report describes the geophysical logging of the deep boreholes that was conducted in support of the Seismic Boreholes Project, defined below. The detailed drilling and geological descriptions of the boreholes and seismic data collected and analysis of that data are reported elsewhere.

  11. Transforming trash: reuse as a waste management and climate change mitigation strategy

    E-Print Network [OSTI]

    Vergara, Sintana Eugenia

    2011-01-01T23:59:59.000Z

    Biological treatment of waste solids. Waste Management andOF POLLUTANTS FROM SOLID WASTE Solid waste affects the32 5. Solid waste and its impact on the

  12. Baseline Flowsheet Generation for the Treatment and Disposal of Idaho National Engineering and Environmental Laboratory Sodium Bearing Waste

    SciTech Connect (OSTI)

    Barnes, C.M.; Lauerhass, L.; Olson, A.L.; Taylor, D.D.; Valentine, J.H.; Lockie, K.A. (DOE- ID)

    2002-01-16T23:59:59.000Z

    The High-Level Waste (HLW) Program at the Idaho National Engineering and Environmental Laboratory (INEEL) must implement technologies and processes to treat and qualify radioactive wastes located at the Idaho Nuclear Technology and Engineering Center (INTEC) for permanent disposal. This paper describes the approach and accomplishments to date for completing development of a baseline vitrification treatment flowsheet for sodium-bearing waste (SBW), including development of a relational database used to manage the associated process assumptions. A process baseline has been developed that includes process requirements, basis and assumptions, process flow diagrams, a process description, and a mass balance. In the absence of actual process or experimental results, mass and energy balance data for certain process steps are based on assumptions. Identification, documentation, validation, and overall management of the flowsheet assumptions are critical to ensuring an integrated, focused program. The INEEL HLW Program initially used a roadmapping methodology, developed through the INEEL Environmental Management Integration Program, to identify, document, and assess the uncertainty and risk associated with the SBW flowsheet process assumptions. However, the mass balance assumptions, process configuration and requirements should be accessible to all program participants. This need resulted in the creation of a relational database that provides formal documentation and tracking of the programmatic uncertainties related to the SBW flowsheet.

  13. Baseline Flowsheet Generation for the Treatment and Disposal of Idaho National Engineering and Environmental Laboratory Sodium Bearing Waste

    SciTech Connect (OSTI)

    Barnes, Charles Marshall; Lauerhass, Lance; Olson, Arlin Leland; Taylor, Dean Dalton; Valentine, James Henry; Lockie, Keith Andrew

    2002-02-01T23:59:59.000Z

    The High-Level Waste (HLW) Program at the Idaho National Engineering and Environmental Laboratory (INEEL) must implement technologies and processes to treat and qualify radioactive wastes located at the Idaho Nuclear Technology and Engineering Center (INTEC) for permanent disposal. This paper describes the approach and accomplishments to date for completing development of a baseline vitrification treatment flowsheet for sodium-bearing waste (SBW), including development of a relational database used to manage the associated process assumptions. A process baseline has been developed that includes process requirements, basis and assumptions, process flow diagrams, a process description, and a mass balance. In the absence of actual process or experimental results, mass and energy balance data for certain process steps are based on assumptions. Identification, documentation, validation, and overall management of the flowsheet assumptions are critical to ensuring an integrated, focused program. The INEEL HLW Program initially used a roadmapping methodology, developed through the INEEL Environmental Management Integration Program, to identify, document, and assess the uncertainty and risk associated with the SBW flowsheet process assumptions. However, the mass balance assumptions, process configuration and requirements should be accessible to all program participants. This need resulted in the creation of a relational database that provides formal documentation and tracking of the programmatic uncertainties related to the SBW flowsheet.

  14. Phase 2 TWR Steam Reforming Test for Sodium-Bearing Waste Treatment

    SciTech Connect (OSTI)

    Nicholas R. Soelberg; Doug Marshall; Dean Taylor; Steven Bates

    2004-01-01T23:59:59.000Z

    About one million gallons of acidic, hazardous, and radioactive sodium-bearing waste (SBW) is stored in stainless steel tanks a the Idaho Nuclear Technology and Engineering Center (INTEC), which is a major operating facility of the Idaho National Engineering and Environmental Laboratory (INEEL). Steam reforming is a candidate technology being investigated for converting the SBW into a road ready waste form that can be shipped to the Waste Isolation Pilot Plant in New Mexico for interment. Fluidized bed steam reforming technology, licensed to ThermoChem Waste Remediation, LLC (TWR) by Manufacturing Technology Conversion International, was tested in two phases using an INEEL (Department of Energy) fluidized bed test system located at the Science Applications International Corporation (SAIC) Science and Technology Applications Research Center in Idaho Falls, Idaho. The Phase 1 tests were reported earlier. The Phase 2 tests are reported here. For Phase 2, the process feed rate, reductant stoichiometry, and process temperature were varied to identify and demonstrate how the process might be optimized to improve operation and product characteristics. The first week of testing was devoted primarily to process chemistry and the second week was devoted more toward bed stability and particle size control.

  15. Alkaline chemistry of transuranium elements and technetium and the treatment of alkaline radioactive wastes

    SciTech Connect (OSTI)

    Delegard, C.H. [Westinghouse Hanford Co., Richland, WA (United States); Peretrukhin, V.F.; Shilov, V.P.; Pikaev, A.K. [Russian Academy of Sciences (Russian Federation). Inst. of Physical Chemistry

    1995-05-01T23:59:59.000Z

    Goal of this survey is to generalize the known data on fundamental physical-chemical properties of TRUs and Tc, methods for their isolation, and to provide recommendations that will be useful for partitioning them from alkaline high-level wastes.

  16. Polyoxometalates for Radioactive Waste Treatment - Final Report - 06/15/1996 - 09/14/2000

    SciTech Connect (OSTI)

    Pope, Michael T.

    2000-09-14T23:59:59.000Z

    The research was directed primarily towards the use of polyoxometalate complexes for separation of lanthanide, actinide, and technetium species from aqueous waste solutions, such as the Hanford Tank Wastes. Selective binding of these species responsible for much of the high level waste (HWL) activity, can reduce the volume of material to be subsequently vitrified or otherwise converted for long-term storage. A secondary objective was to explore the direct conversion of the polyoxometalate complexes into possible waste forms, oxide bronzes, thereby avoiding additional handling and energy-intensive vitrification procedures. Although the advantages of polyoxometalate anions (POMs) lie in their high thermal and radiolytical stabilities, that has been no attempt to exploit the remarkable variety of these complexes beyond the use of the two anions mentioned above. Our broad knowledge of POM chemistry has allowed us to address and rectify this omission. The innovative aspects of the project are: (a) the selective sequestration of lanthanide and actinide cations by a POM system in the presence of excess alkali and transition metal cations; (b) the formation of the first examples of POM complexes of UO2-2+ and their extraction into nonaqueous solvents; (c) the thermal conversion of ammonium salts of lanthanide and actinide POM complexes into inert oxide bronzes at relatively low temperatures; and (d) the direct formation of highly thermally-robust niobate and tantalate complexes of Re (surrogate for Tc) in highly basic solutions.

  17. The impact of municipal solid waste treatment methods on greenhouse gas emissions in Lahore, Pakistan

    SciTech Connect (OSTI)

    Batool, Syeda Adila [Department of Space Science, Punjab University, Lahore 54600 (Pakistan)], E-mail: aadila_batool@yahoo.com; Chuadhry, Muhammad Nawaz [College of Earth and Environmental Sciences, University of the Punjab, Lahore (Pakistan)], E-mail: muhammadnawazchaudhry@yahoo.com

    2009-01-15T23:59:59.000Z

    The contribution of existing municipal solid waste management to emission of greenhouse gases and the alternative scenarios to reduce emissions were analyzed for Data Ganj Bukhsh Town (DGBT) in Lahore, Pakistan using the life cycle assessment methodology. DGBT has a population of 1,624,169 people living in 232,024 dwellings. Total waste generated is 500,000 tons per year with an average per capita rate of 0.84 kg per day. Alternative scenarios were developed and evaluated according to the environmental, economic, and social atmosphere of the study area. Solid waste management options considered include the collection and transportation of waste, collection of recyclables with single and mixed material bank container systems (SMBCS, MMBCS), material recovery facilities (MRF), composting, biogasification and landfilling. A life cycle inventory (LCI) of the six scenarios along with the baseline scenario was completed; this helped to quantify the CO{sub 2} equivalents, emitted and avoided, for energy consumption, production, fuel consumption, and methane (CH{sub 4}) emissions. LCI results showed that the contribution of the baseline scenario to the global warming potential as CO{sub 2} equivalents was a maximum of 838,116 tons. The sixth scenario had a maximum reduction of GHG emissions in terms of CO{sub 2} equivalents of -33,773 tons, but the most workable scenario for the current situation in the study area is scenario 5. It saves 25% in CO{sub 2} equivalents compared to the baseline scenario.

  18. Yucca Mountain project canister material corrosion studies as applied to the electrometallurgical treatment metallic waste form

    SciTech Connect (OSTI)

    Keiser, D.D.

    1996-11-01T23:59:59.000Z

    Yucca Mountain, Nevada is currently being evaluated as a potential site for a geologic repository. As part of the repository assessment activities, candidate materials are being tested for possible use as construction materials for waste package containers. A large portion of this testing effort is focused on determining the long range corrosion properties, in a Yucca Mountain environment, for those materials being considered. Along similar lines, Argonne National Laboratory is testing a metallic alloy waste form that also is scheduled for disposal in a geologic repository, like Yucca Mountain. Due to the fact that Argonne`s waste form will require performance testing for an environment similar to what Yucca Mountain canister materials will require, this report was constructed to focus on the types of tests that have been conducted on candidate Yucca Mountain canister materials along with some of the results from these tests. Additionally, this report will discuss testing of Argonne`s metal waste form in light of the Yucca Mountain activities.

  19. Evaluating In Situ Treatment Technologies for Buried Mixed Waste Remediation at the INEEL

    SciTech Connect (OSTI)

    D.F. Nickelson; D.K. Jorgensen; J.J. Jessmore; R.A. Hyde; R.K. Farnsworth

    1999-02-01T23:59:59.000Z

    Mixed radioactive and hazardous wastes were buried at the Department of Energy's Idaho National Engineering and Environmental Laboratory (INEEL) Subsurface Disposal Area from 1952 to 1969. To begin the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) remediation process for the Subsurface Disposal Area, the Environmental Protection Agency (EPA) added the INEEL to its National Priorities List in 1989. DOE's Office of Environmental Restoration is planning several CERCLA treatability studies of remedial technologies that will be evaluated for potential remediation of the buried waste in the Subsurface Disposal Area. This paper discusses the in situ treatability studies that will be performed, including in situ vitrification, in situ grouting, and in situ thermal desorption. The in situ treatability studies will be conducted on simulated and actual buried wastes at the INEEL in 1999 and 2000. Results from the treatability studies will provide substantial information on the feasibility, implementability, and cost of applying these technologies to the INEEL Subsurface Disposal Area. In addition, much of the treatability study data will be applicable to buried waste site remediation efforts across the DOE complex.

  20. Evaluating In Situ Treatment Technologies for Buried Mixed Waste Remediation at the INEEL

    SciTech Connect (OSTI)

    Jorgensen, Douglas Kay; Nickelson, David Frank; Nickelson, Reva Anne; Farnsworth, Richard Kent; Jessmore, James Joseph

    1999-03-01T23:59:59.000Z

    Mixed radioactive and hazardous wastes were buried at the Department of Energy’s Idaho National Engineering and Environmental Laboratory (INEEL) Subsurface Disposal Area from 1952 to 1969. To begin the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) remediation process for the Subsurface Disposal Area, the Environmental Protection Agency (EPA) added the INEEL to its National Priorities List in 1989. DOE’s Office of Environmental Restoration is planning several CERCLA treatability studies of remedial technologies that will be evaluated for potential remediation of the buried waste in the Subsurface Disposal Area. This paper discusses the in situ treatability studies that will be performed, including in situ vitrification, in situ grouting, and in situ thermal desorption. The in situ treatability studies will be conducted on simulated and actual buried wastes at the INEEL in 1999 and 2000. Results from the treatability studies will provide substantial information on the feasibility, implementability, and cost of applying these technologies to the INEEL Subsurface Disposal Area. In addition, much of the treatability study data will be applicable to buried waste site remediation efforts across the DOE complex.

  1. Thermochemical conversion of waste materials to valuable products

    SciTech Connect (OSTI)

    Saraf, S. [Engineering Technologies, Lombard, IL (United States)

    1997-12-31T23:59:59.000Z

    The potential offered by a large variety of solid and liquid wastes for generating value added products is widely recognized. Extensive research and development has focused on developing technologies to recover energy and valuable products from waste materials. These treatment technologies include use of waste materials for direct combustion, upgrading the waste materials into useful fuel such as fuel gas or fuel oil, and conversion of waste materials into higher value products for the chemical industry. Thermal treatment in aerobic (with oxygen) conditions or direct combustion of waste materials in most cases results in generating air pollution and thereby requiring installation of expensive control devices. Thermochemical conversion in aerobic (without oxygen) conditions, referred to as thermal decomposition (destructive distillation) results in formation of usable liquid, solid, and gaseous products. Thermochemical conversion includes gasification, liquefaction, and thermal decomposition (pyrolysis). Each thermochemical conversion process yields a different range of products and this paper will discuss thermal decomposition in detail. This paper will also present results of a case study for recovering value added products, in the form of a liquid, solid, and gas, from thermal decomposition of waste oil and scrap tires. The product has a high concentration of benzene, xylene, and toluene. The solid product has significant amounts of carbon black and can be used as an asphalt modifier for road construction. The gas product is primarily composed of methane and is used for heating the reactor.

  2. Integrated nonthermal treatment system study

    SciTech Connect (OSTI)

    Biagi, C.; Bahar, D.; Teheranian, B.; Vetromile, J. [Morrison Knudsen Corp. (United States); Quapp, W.J. [Nuclear Metals (United States); Bechtold, T.; Brown, B.; Schwinkendorf, W. [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States); Swartz, G. [Swartz and Associates (United States)

    1997-01-01T23:59:59.000Z

    This report presents the results of a study of nonthermal treatment technologies. The study consisted of a systematic assessment of five nonthermal treatment alternatives. The treatment alternatives consist of widely varying technologies for safely destroying the hazardous organic components, reducing the volume, and preparing for final disposal of the contact-handled mixed low-level waste (MLLW) currently stored in the US Department of Energy complex. The alternatives considered were innovative nonthermal treatments for organic liquids and sludges, process residue, soil and debris. Vacuum desorption or various washing approaches are considered for treatment of soil, residue and debris. Organic destruction methods include mediated electrochemical oxidation, catalytic wet oxidation, and acid digestion. Other methods studied included stabilization technologies and mercury separation of treatment residues. This study is a companion to the integrated thermal treatment study which examined 19 alternatives for thermal treatment of MLLW waste. The quantities and physical and chemical compositions of the input waste are based on the inventory database developed by the US Department of Energy. The Integrated Nonthermal Treatment Systems (INTS) systems were evaluated using the same waste input (2,927 pounds per hour) as the Integrated Thermal Treatment Systems (ITTS). 48 refs., 68 figs., 37 tabs.

  3. Office of River Protection (DOE-ORP) Hanford Tank Waste Treatment Alternatives March 2000

    SciTech Connect (OSTI)

    WODRICH, D.D.

    2000-03-24T23:59:59.000Z

    The U.S. Department of Energy (DOE) is currently planning to retrieve, pretreat, immobilize and safely dispose of 53 million gallons of highly radioactive waste currently stored in underground tanks at Hanford Site. The DOE plan is a two-phased approach to privatizing the processing of hazardous and radioactive waste. Phase 1 is a proof-of-concept/commercial demonstration-scale effort whose objectives are to: demonstrate, the technical and business viability of using privatized facilities to treat Hanford tank waste; define and maintain required levels of radiological, nuclear, process and occupational safety; maintain environmental protection and compliance; and substantially reduce life-cycle costs and time required to treat Hanford tank waste. The Phase 1 effort consists of Part A and Part B. On September 25, 1996 (Reference 1), DOE signed a contract with BNFL, Inc. (BNFL) to commence with Phase 1, Part A. In August 1998, BNFL was authorized to proceed with Phase I, Part 6-1, a 24-month design phase that will-provide sufficient engineering and financial maturity to establish fixed-unit prices and financing terms for tank waste processing services in privately-owned and -operated facilities. By August 2000, DOE will decide whether to authorize BNFL to proceed with construction and operation of the proposed processing facilities, or pursue a different path. To support of the decision, DOE is evaluating alternatives to potentially enhance the BNFL tank waste processing contract, as well as, developing an alternate path forward should DOE decide to not continue the BNFL contract. The decision on whether to continue with the current privatization strategy (BNFL contract) or to pursue an alternate can not be made until the evaluation process leading up to the decision on whether to authorize BNFL to proceed with construction and operation (known as the Part 8-2 decision) is completed. The evaluation process includes reviewing and evaluating the information BNFL is scheduled to submit in April 2000, and negotiating the best mutually acceptable contract terms. The alternatives studies completed to-date are summarized in Reference 2.

  4. Liquid effluent/Hanford Environmental compliance FY 1995 Multi-Year Program Plan/Fiscal Year Work Plan, WBS 1.2.2.1 and 1.2.2.2

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    This document details the program effort to eliminate the use of the soil column for liquid effluent treatment and to manage current and future liquid effluent streams at the Hanford Site, in a safe responsible cost effective and legally compliant mannger. This should be achieved through planning, public and stakeholder interaction, definition of requiremtns for generators, and provision of timely treatment, stroage, disposal capability, and waste minimization of waste streams.

  5. Wastewater and Wastewater Treatment Systems (Oklahoma)

    Broader source: Energy.gov [DOE]

    The Oklahoma Department of Environmental Quality administers regulations for waste water and waste water treatment systems. Construction of a municipal treatment work, non-industrial waste water...

  6. Secondary waste form testing : ceramicrete phosphate bonded ceramics.

    SciTech Connect (OSTI)

    Singh, D.; Ganga, R.; Gaviria, J.; Yusufoglu, Y. (Nuclear Engineering Division); ( ES)

    2011-06-21T23:59:59.000Z

    The cleanup activities of the Hanford tank wastes require stabilization and solidification of the secondary waste streams generated from the processing of the tank wastes. The treatment of these tank wastes to produce glass waste forms will generate secondary wastes, including routine solid wastes and liquid process effluents. Liquid wastes may include process condensates and scrubber/off-gas treatment liquids from the thermal waste treatment. The current baseline for solidification of the secondary wastes is a cement-based waste form. However, alternative secondary waste forms are being considered. In this regard, Ceramicrete technology, developed at Argonne National Laboratory, is being explored as an option to solidify and stabilize the secondary wastes. The Ceramicrete process has been demonstrated on four secondary waste formulations: baseline, cluster 1, cluster 2, and mixed waste streams. Based on the recipes provided by Pacific Northwest National Laboratory, the four waste simulants were prepared in-house. Waste forms were fabricated with three filler materials: Class C fly ash, CaSiO{sub 3}, and Class C fly ash + slag. Optimum waste loadings were as high as 20 wt.% for the fly ash and CaSiO{sub 3}, and 15 wt.% for fly ash + slag filler. Waste forms for physical characterizations were fabricated with no additives, hazardous contaminants, and radionuclide surrogates. Physical property characterizations (density, compressive strength, and 90-day water immersion test) showed that the waste forms were stable and durable. Compressive strengths were >2,500 psi, and the strengths remained high after the 90-day water immersion test. Fly ash and CaSiO{sub 3} filler waste forms appeared to be superior to the waste forms with fly ash + slag as a filler. Waste form weight loss was {approx}5-14 wt.% over the 90-day immersion test. The majority of the weight loss occurred during the initial phase of the immersion test, indicative of washing off of residual unreacted binder components from the waste form surface. Waste forms for ANS 16.1 leach testing contained appropriate amounts of rhenium and iodine as radionuclide surrogates, along with the additives silver-loaded zeolite and tin chloride. The leachability index for Re was found to range from 7.9 to 9.0 for all the samples evaluated. Iodine was below detection limit (5 ppb) for all the leachate samples. Further, leaching of sodium was low, as indicated by the leachability index ranging from 7.6-10.4, indicative of chemical binding of the various chemical species. Target leachability indices for Re, I, and Na were 9, 11, and 6, respectively. Degradation was observed in some of the samples post 90-day ANS 16.1 tests. Toxicity characteristic leaching procedure (TCLP) results showed that all the hazardous contaminants were contained in the waste, and the hazardous metal concentrations were below the Universal Treatment Standard limits. Preliminary scale-up (2-gal waste forms) was conducted to demonstrate the scalability of the Ceramicrete process. Use of minimal amounts of boric acid as a set retarder was used to control the working time for the slurry. Flexibility in treating waste streams with wide ranging compositional make-ups and ease of process scale-up are attractive attributes of Ceramicrete technology.

  7. Engineering-Scale Demonstration of DuraLith and Ceramicrete Waste Forms

    SciTech Connect (OSTI)

    Josephson, Gary B.; Westsik, Joseph H.; Pires, Richard P.; Bickford, Jody; Foote, Martin W.

    2011-09-23T23:59:59.000Z

    To support the selection of a waste form for the liquid secondary wastes from the Hanford Waste Immobilization and Treatment Plant, Washington River Protection Solutions (WRPS) has initiated secondary waste form testing on four candidate waste forms. Two of the candidate waste forms have not been developed to scale as the more mature waste forms. This work describes engineering-scale demonstrations conducted on Ceramicrete and DuraLith candidate waste forms. Both candidate waste forms were successfully demonstrated at an engineering scale. A preliminary conceptual design could be prepared for full-scale production of the candidate waste forms. However, both waste forms are still too immature to support a detailed design. Formulations for each candidate waste form need to be developed so that the material has a longer working time after mixing the liquid and solid constituents together. Formulations optimized based on previous lab studies did not have sufficient working time to support large-scale testing. The engineering-scale testing was successfully completed using modified formulations. Further lab development and parametric studies are needed to optimize formulations with adequate working time and assess the effects of changes in raw materials and process parameters on the final product performance. Studies on effects of mixing intensity on the initial set time of the waste forms are also needed.

  8. Product consistency test and toxicity characteristic leaching procedure results of the ceramic waste form from the electrometallurgical treatment process for spent fuel

    SciTech Connect (OSTI)

    Johnson, S. G.; Adamic, M. L.: DiSanto, T.; Warren, A. R.; Cummings, D. G.; Foulkrod, L.; Goff, K. M.

    1999-11-11T23:59:59.000Z

    The ceramic waste form produced from the electrometallurgical treatment of sodium bonded spent fuel from the Experimental Breeder Reactor-II was tested using two immersion tests with separate and distinct purposes. The product consistency test is used to assess the consistency of the waste forms produced and thus is an indicator of a well-controlled process. The toxicity characteristic leaching procedure is used to determine whether a substance is to be considered hazardous by the Environmental Protection Agency. The proposed high level waste repository will not be licensed to receive hazardous waste, thus any waste forms destined to be placed there cannot be of a hazardous nature as defined by the Resource Conservation and Recovery Act. Results are presented from the first four fully radioactive ceramic waste forms produced and from seven ceramic waste forms produced from cold surrogate materials. The fully radioactive waste forms are approximately 2 kg in weight and were produced wit h salt used to treat 100 driver subassemblies of spent fuel.

  9. Proceedings of the 1993 international conference on nuclear waste management and environmental remediation. Volume 3: Environmental remediation and environmental management issues

    SciTech Connect (OSTI)

    Baschwitz, R.; Kohout, R.; Marek, J.; Richter, P.I.; Slate, S.C. [eds.

    1993-12-31T23:59:59.000Z

    This conference was held in 1993 in Prague, Czech Republic to provide a forum for exchange of state-of-the-art information on radioactive waste management. Papers are divided into the following sections: Low/Intermediate level waste disposal from an international viewpoint; Solid waste volume reduction, treatment and packaging experience; Design of integrated systems for management of nuclear wastes; Mixed waste (hazardous and radioactive) treatment and disposal; Advanced low/intermediate level waste conditioning technologies including incineration; National programs for low/intermediate waste management; Low/Intermediate waste characterization, assay, and tracking systems; Disposal site characterization and performance assessment; Radioactive waste management and practices in developing countries; Waste management from unconventional (e.g. VVER) nuclear power reactors; Waste minimization, avoidance and recycling in nuclear power plants; Liquid waste treatment processes and experience; Low/Intermediate waste storage facilities--design and experience; Low/Intermediate waste forms and acceptance criteria for disposal; Management of non-standard or accident waste; and Quality assurance and control in nuclear waste management. Individual papers have been processed separately for inclusion in the appropriate data bases.

  10. Heterogeneous waste processing

    DOE Patents [OSTI]

    Vanderberg, Laura A. (Los Alamos, NM); Sauer, Nancy N. (Los Alamos, NM); Brainard, James R. (Los Alamos, NM); Foreman, Trudi M. (Los Alamos, NM); Hanners, John L. (Los Alamos, NM)

    2000-01-01T23:59:59.000Z

    A combination of treatment methods are provided for treatment of heterogeneous waste including: (1) treatment for any organic compounds present; (2) removal of metals from the waste; and, (3) bulk volume reduction, with at least two of the three treatment methods employed and all three treatment methods emplyed where suitable.

  11. Asit Nema\\Foundation Green-Ensys 1 RISK FACTORS ASSOCIATED WITH SOLID WASTE TREATMENT

    E-Print Network [OSTI]

    Columbia University

    that 285 million urban population in India ( 28% of the total population) is generating almost 120,000 MT of the entire chain of operations. A number of ULBs have gone about setting up treatment plants under treatment plants and one disposal facility from across India was carried out with the objective of assessing

  12. A UA study confirms that uncontrolled e-waste treatment produces carcinogenic effects

    E-Print Network [OSTI]

    Escolano, Francisco

    (WEEE) are not treated properly. In this sense, once reused and recycled in treatment plants, electronic. Its main objective is to analyse the effect of the presence of metals during the WEEE treatment tonnes of WEEE were generated in Europe. In Spain, the figure amounted to 800 thousand tonnes, equivalent

  13. DECISION SUPPORT FOR A WASTE ELECTRICAL AND ELECTRONIC EQUIPMENT TREATMENT SYSTEM

    E-Print Network [OSTI]

    Bohanec, Marko

    and Electronic Equipment (WEEE) treatment system in the development of incineration, disposal, treatment and recycling integrated programs. In the paper, we describe the WEEE, taking a broad view of various types of decisions in the field of WEEE. A detailed explanation of the decisions in the WEEE Logistics is given

  14. Correlation of radioactive-waste-treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle: conversion of yellow cake to uranium hexafluoride. Part II. The solvent extraction-fluorination process

    SciTech Connect (OSTI)

    Sears, M.B.; Etnier, E.L.; Hill, G.S.; Patton, B.D.; Witherspoon, J.P.; Yen, S.N.

    1983-03-01T23:59:59.000Z

    A cost/benefit study was made to determine the cost and effectiveness of radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials and chemicals from a model uranium hexafluoride (UF/sub 6/) production plant using the solvent extraction-fluorination process, and to evaluate the radiological impact (dose commitment) of the release materials on the environment. The model plant processes 10,000 metric tons of uranium per year. Base-case waste treatment is the minimum necessary to operate the process. Effluents meet the radiological requirements listed in the Code of Federal Regulations, Title 10, Part 20 (10 CFR 20), Appendix B, Table II, but may not be acceptable chemically at all sites. Additional radwaste treatment techniques are applied to the base-case plant in a series of case studies to decrease the amounts of radioactive materials released and to reduce the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The costs for the added waste treatment operations and the corresponding dose committment are correlated with the annual cost for treatment of the radwastes. The status of the radwaste treatment methods used in the case studies is discussed. Much of the technology used in the advanced cases will require development and demonstration, or else is proprietary and unavailable for immediate use. The methodology and assumptions for the radiological doses are found in ORNL-4992.

  15. The effect of high pH chemical hydrolysis on biological waste treatment

    E-Print Network [OSTI]

    Smullen, Richard Frederick

    1971-01-01T23:59:59.000Z

    waste waters to create a recreational lake. Again the major consideration of the reduction in phosphate was to control algal growth. In this case alum was chosen as the primary coagulant. Laboratory analysis demonstrated that alum was slightly... (ll) lime sludge is more easily dewatered than is iron sludge or alum sludge. This proves even more beneficial when you consider that lime sludge can be regenerated. The equation for lime sludge recovery is as follows: 10 Ilt 1000 F CaC03 ? ~ Ca0...

  16. Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality, May 2013

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn April 23, 2014, anEnergy nepdg_5251_5500.pdfAnalysis of Downwash fromWaste

  17. Review of the Hanford Site Waste Treatment and Immobilization Plant Project Construction Quality, March 2012

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn April 23, 2014, anEnergy nepdg_5251_5500.pdfAnalysis of Downwash fromWaste Hanford

  18. Overview of Pulse Jet Mixer/Hybrid Mixing System Development to Support the Hanford Waste Treatment Plant

    SciTech Connect (OSTI)

    Kurath, Dean E.; Meyer, Perry A.; Stewart, Charles W.; Barnes, Steven M.

    2006-03-02T23:59:59.000Z

    The U.S. Department of Energy (DOE) Office of River Protection's Waste Treatment Plant (WTP) will process and treat radioactive waste that is stored in underground tanks at the Hanford Site. Pulse jet mixer (PJM) technology was selected for mixing the contents of many of the process vessels. Several of the tanks are expected to contain concentrated slurries that exhibit a non-Newtonian rheology and the understanding required to apply this technology to mobilize the non-Newtonian slurries was not mature. Consequently, an experimental testing effort was undertaken to investigate PJM performance in several scaled versions of WTP vessels and to develop mixing system configurations that met WTP requirements. This effort evolved into a large, multifaceted test program involving many different test facilities. Elements of the test program included theoretical analysis, development and characterization of simulants, development of instrumentation and measurement techniques, hundreds of tests at various scales in numerous test stands, and data analysis and application. This program provided the technical basis for the selection of pulse jet mixers along with air spargers and steady jets generated by recirculation pumps to provide mixing systems for several of the vessels with non-Newtonian slurries. This paper provides an overview of the testing program and a summary of the key technical results that formed the technical basis of the final mixing system configurations to be used in the WTP.

  19. Assessment of sludge management options in a waste water treatment plant

    E-Print Network [OSTI]

    Lim, Jong hyun, M. Eng. Massachusetts Institute of Technology

    2012-01-01T23:59:59.000Z

    This thesis is part of a larger project which began in response to a request by the Spanish water agengy, Cadagua, for advice on life cycle assessment (LCA) and environmental impacts of Cadagua operated wastewater treatment ...

  20. The Potential of Cellulosic Ethanol Production from Municipal Solid Waste: A Technical and Economic Evaluation

    E-Print Network [OSTI]

    Shi, Jian; Ebrik, Mirvat; Yang, Bin; Wyman, Charles E.

    2009-01-01T23:59:59.000Z

    e.g. waste water treatment, solid waste combustion) weretreatments. Results and Discussions Cellulosic MSW Feedstocks Municipal solid waste (

  1. Secondary Waste Form Down Selection Data Package – Ceramicrete

    SciTech Connect (OSTI)

    Cantrell, Kirk J.; Westsik, Joseph H.

    2011-08-31T23:59:59.000Z

    As part of high-level waste pretreatment and immobilized low activity waste processing, liquid secondary wastes will be generated that will be transferred to the Effluent Treatment Facility on the Hanford Site for further treatment. These liquid secondary wastes will be converted to stable solid waste forms that will be disposed in the Integrated Disposal Facility. Currently, four waste forms are being considered for stabilization and solidification of the liquid secondary wastes. These waste forms are Cast Stone, Ceramicrete, DuraLith, and Fluidized Bed Steam Reformer. The preferred alternative will be down selected from these four waste forms. Pacific Northwest National Laboratory is developing data packages to support the down selection process. The objective of the data packages is to identify, evaluate, and summarize the existing information on the four waste forms being considered for stabilization and solidification of the liquid secondary wastes. The information included will be based on information available in the open literature and from data obtained from testing currently underway. This data package is for the Ceramicrete waste form. Ceramicrete is a relatively new engineering material developed at Argonne National Laboratory to treat radioactive and hazardous waste streams (e.g., Wagh 2004; Wagh et al. 1999a, 2003; Singh et al. 2000). This cement-like waste form can be used to treat solids, liquids, and sludges by chemical immobilization, microencapsulation, and/or macroencapsulation. The Ceramicrete technology is based on chemical reaction between phosphate anions and metal cations to form a strong, dense, durable, low porosity matrix that immobilizes hazardous and radioactive contaminants as insoluble phosphates and microencapsulates insoluble radioactive components and other constituents that do not form phosphates. Ceramicrete is a type of phosphate-bonded ceramic, which are also known as chemically bonded phosphate ceramics. The Ceramicrete binder is formed through an acid-base reaction between calcined magnesium oxide (MgO; a base) and potassium hydrogen phosphate (KH{sub 2}PO{sub 4}; an acid) in aqueous solution. The reaction product sets at room temperature to form a highly crystalline material. During the reaction, the hazardous and radioactive contaminants also react with KH{sub 2}PO{sub 4} to form highly insoluble phosphates. In this data package, physical property and waste acceptance data for Ceramicrete waste forms fabricated with wastes having compositions that were similar to those expected for secondary waste effluents, as well as secondary waste effluent simulants from the Hanford Tank Waste Treatment and Immobilization Plant were reviewed. With the exception of one secondary waste form formulation (25FA+25 W+1B.A. fabricated with the mixed simulant did not meet the compressive strength requirement), all the Ceramicrete waste forms that were reviewed met or exceeded Integrated Disposal Facility waste acceptance criteria.

  2. Development of Site-Specific Soil Design Basis Earthquake (DBE) Parameters for the Integrated Waste Treatment Unit (IWTU)

    SciTech Connect (OSTI)

    Payne, Suzette

    2008-08-01T23:59:59.000Z

    Horizontal and vertical PC 3 (2,500 yr) Soil Design Basis Earthquake (DBE) 5% damped spectra, corresponding time histories, and strain-compatible soil properties were developed for the Integrated Waste Treatment Unit (IWTU). The IWTU is located at the Idaho Nuclear Technology and Engineering Center (INTEC) at the Idaho National Laboratory (INL). Mean and 84th percentile horizontal DBE spectra derived from site-specific site response analyses were evaluated for the IWTU. The horizontal and vertical PC 3 (2,500 yr) Soil DBE 5% damped spectra at the 84th percentile were selected for Soil Structure Interaction (SSI) analyses at IWTU. The site response analyses were performed consistent with applicable Department of Energy (DOE) Standards, recommended guidance of the Nuclear Regulatory Commission (NRC), American Society of Civil Engineers (ASCE) Standards, and recommendations of the Blue Ribbon Panel (BRP) and Defense Nuclear Facilities Safety Board (DNFSB).

  3. Technical area status report for chemical/physical treatment. Volume 1

    SciTech Connect (OSTI)

    Brown, C.H. Jr. [Oak Ridge National Lab., TN (United States); Schwinkendorf, W.E. [BDM Federal, Inc., Arlington, VA (United States)

    1993-08-01T23:59:59.000Z

    The Office of Environmental Restoration and Waste Management (EM) was established by the Department of Energy (DOE) to direct and coordinate waste management and site remediation programs and activities throughout the DOE Complex. The Mixed Waste Integrated Program (MWIP) was created by the DOE Office of Technology Development (OTD) to develop, deploy, and complete appropriate technologies for the treatment of an DOE low-level mixed waste (LLMW). The MWIP mission includes development of strategies related to enhanced waste form production, improvements to and testing of the EM-30 baseline flowsheet for mixed waste treatment, programmatic oversight for ongoing technical projects, and specific technical tasks related to the site specific Federal Facilities Compliance Agreement (FFCA). The MWIP has established five Technical Support Groups (TSGs) based on primary functional areas of the Mixed Waste Treatment Plant) identified by EM-30. These TSGs are: (1) Front-End Waste Handling, (2) Chemical/Physical Treatment, (3) Waste Destruction and Stabilization, (4) Second-stage Destruction and Offgas Treatment, and (5) Final Waste Forms. The focus of this document is the Chemical/Physical Treatment System (CPTS). The CPTS performs the required pretreatment and/or separations on the waste streams passing through the system for discharge to the environment or efficient downstream processing. Downstream processing can include all system components except Front-End Waste Handling. The primary separations to be considered by the CPTS are: (1) removal of suspended and dissolved solids from aqueous and liquid organic streams, (2) separation of water from organic liquids, (3) treatment of wet and dry solids, including separation into constituents as required, for subsequent thermal treatment and final form processing, (4) mercury removal and control, and (5) decontamination of equipment and waste classified as debris.

  4. Municipal Solid Waste (MSW) to Liquid Fuels Synthesis, Volume 2: A Techno-economic Evaluation of the Production of Mixed Alcohols

    SciTech Connect (OSTI)

    Jones, Susanne B.; Zhu, Yunhua; Valkenburt, Corinne

    2009-05-01T23:59:59.000Z

    Biomass is a renewable energy resource that can be converted into liquid fuel suitable for transportation applications and thus help meet the Energy Independence and Security Act renewable energy goals (U.S. Congress 2007). However, biomass is not always available in sufficient quantity at a price compatible with fuels production. Municipal solid waste (MSW) on the other hand is readily available in large quantities in some communities and is considered a partially renewable feedstock. Furthermore, MSW may be available for little or no cost. This report provides a techno-economic analysis of the production of mixed alcohols from MSW and compares it to the costs for a wood based plant. In this analysis, MSW is processed into refuse derived fuel (RDF) and then gasified in a plant co-located with a landfill. The resulting syngas is then catalytically converted to mixed alcohols. At a scale of 2000 metric tons per day of RDF, and using current technology, the minimum ethanol selling price at a 10% rate of return is approximately $1.85/gallon ethanol (early 2008 $). However, favorable economics are dependent upon the toxicity characteristics of the waste streams and that a market exists for the by-product scrap metal recovered from the RDF process.

  5. Extraction processes and solvents for recovery of cesium, strontium, rare earth elements, technetium and actinides from liquid radioactive waste

    DOE Patents [OSTI]

    Zaitsev, Boris N. (St. Petersburg, RU); Esimantovskiy, Vyacheslav M. (St. Petersburg, RU); Lazarev, Leonard N. (St. Petersburg, RU); Dzekun, Evgeniy G. (Ozersk, RU); Romanovskiy, Valeriy N. (St. Petersburg, RU); Todd, Terry A. (Aberdeen, ID); Brewer, Ken N. (Arco, ID); Herbst, Ronald S. (Idaho Falls, ID); Law, Jack D. (Pocatello, ID)

    2001-01-01T23:59:59.000Z

    Cesium and strontium are extracted from aqueous acidic radioactive waste containing rare earth elements, technetium and actinides, by contacting the waste with a composition of a complex organoboron compound and polyethylene glycol in an organofluorine diluent mixture. In a preferred embodiment the complex organoboron compound is chlorinated cobalt dicarbollide, the polyethylene glycol has the formula RC.sub.6 H.sub.4 (OCH.sub.2 CH.sub.2).sub.n OH, and the organofluorine diluent is a mixture of bis-tetrafluoropropyl ether of diethylene glycol with at least one of bis-tetrafluoropropyl ether of ethylene glycol and bis-tetrafluoropropyl formal. The rare earths, technetium and the actinides (especially uranium, plutonium and americium), are extracted from the aqueous phase using a phosphine oxide in a hydrocarbon diluent, and reextracted from the resulting organic phase into an aqueous phase by using a suitable strip reagent.

  6. Thirty-year solid waste generation forecast for facilities at SRS

    SciTech Connect (OSTI)

    Not Available

    1994-07-01T23:59:59.000Z

    The information supplied by this 30-year solid waste forecast has been compiled as a source document to the Waste Management Environmental Impact Statement (WMEIS). The WMEIS will help to select a sitewide strategic approach to managing present and future Savannah River Site (SRS) waste generated from ongoing operations, environmental restoration (ER) activities, transition from nuclear production to other missions, and decontamination and decommissioning (D&D) programs. The EIS will support project-level decisions on the operation of specific treatment, storage, and disposal facilities within the near term (10 years or less). In addition, the EIS will provide a baseline for analysis of future waste management activities and a basis for the evaluation of the specific waste management alternatives. This 30-year solid waste forecast will be used as the initial basis for the EIS decision-making process. The Site generates and manages many types and categories of waste. With a few exceptions, waste types are divided into two broad groups-high-level waste and solid waste. High-level waste consists primarily of liquid radioactive waste, which is addressed in a separate forecast and is not discussed further in this document. The waste types discussed in this solid waste forecast are sanitary waste, hazardous waste, low-level mixed waste, low-level radioactive waste, and transuranic waste. As activities at SRS change from primarily production to primarily decontamination and decommissioning and environmental restoration, the volume of each waste s being managed will change significantly. This report acknowledges the changes in Site Missions when developing the 30-year solid waste forecast.

  7. Evaluation of gasification and novel thermal processes for the treatment of municipal solid waste

    SciTech Connect (OSTI)

    Niessen, W.R.; Marks, C.H.; Sommerlad, R.E. [Camp Dresser and McKee, Inc., Cambridge, MA (United States)] [Camp Dresser and McKee, Inc., Cambridge, MA (United States)

    1996-08-01T23:59:59.000Z

    This report identifies seven developers whose gasification technologies can be used to treat the organic constituents of municipal solid waste: Energy Products of Idaho; TPS Termiska Processor AB; Proler International Corporation; Thermoselect Inc.; Battelle; Pedco Incorporated; and ThermoChem, Incorporated. Their processes recover heat directly, produce a fuel product, or produce a feedstock for chemical processes. The technologies are on the brink of commercial availability. This report evaluates, for each technology, several kinds of issues. Technical considerations were material balance, energy balance, plant thermal efficiency, and effect of feedstock contaminants. Environmental considerations were the regulatory context, and such things as composition, mass rate, and treatability of pollutants. Business issues were related to likelihood of commercialization. Finally, cost and economic issues such as capital and operating costs, and the refuse-derived fuel preparation and energy conversion costs, were considered. The final section of the report reviews and summarizes the information gathered during the study.

  8. Study on LiCl waste salt treatment process by layer melt crystallization

    SciTech Connect (OSTI)

    Cho, Yung-Zun; Lee, Tae-Kyo; Choi, Jung-Hoon; Eun, Hee-Chul; Park, Hwan-Seo; Kim, In-Tae; Park, Geun-Il [Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

    2013-07-01T23:59:59.000Z

    Layer melt crystallization operated in a static mode has been applied to separate Group I and II chlorides from surrogate LiCl waste salt. The effects of operating conditions such as crystal growing rate(or flux) and initial impurity concentration on separation (or concentration) of cesium, strontium and barium involved in a LiCl melts were analyzed. In a layer crystallization process, separation was impaired by occlusion of impurities and by residual melt adhering to LiCl crystal after at the end of the process. The crystal growth rate strongly affects the crystal structure, therefore the separation efficiency, while the effect of the initial Cs and Sr concentration in LiCl molten salt was nearly negligible. (authors)

  9. Review and Status of Solid Waste Management Practices in Multan, Pakistan

    E-Print Network [OSTI]

    Shoaib, Muhammad; Mirza, Umar Karim; Sarwar, Muhammad Avais

    2006-01-01T23:59:59.000Z

    Resource Center. (2004). Solid waste management study,in management of liquid and solid waste, Multan City, JuneReview and Status of Solid Waste Management Practices in

  10. Vitrified waste option study report

    SciTech Connect (OSTI)

    Lopez, D.A.; Kimmitt, R.R.

    1998-02-01T23:59:59.000Z

    A {open_quotes}Settlement Agreement{close_quotes} between the Department of Energy and the State of Idaho mandates that all radioactive high-level waste (HLW) now stored at the Idaho Chemical Processing Plant (ICPP) will be treated so that it is ready to be moved out of Idaho for disposal by a target date of 2035. This report investigates vitrification treatment of all ICPP calcine, including the existing and future HLW calcine resulting from calcining liquid Sodium-Bearing Waste (SBW). Currently, the SBW is stored in the tank farm at the ICPP. Vitrification of these wastes is an acceptable treatment method for complying with the Settlement Agreement. This method involves vitrifying the calcined waste and casting the vitrified mass into stainless steel canisters that will be ready to be moved out of the Idaho for disposal by 2035. These canisters will be stored at the Idaho National Engineering and Environmental Laboratory (INEEL) until they are sent to a HLW national repository. The operating period for vitrification treatment will be from 2013 through 2032; all HLW will be treated and in storage by the end of 2032.

  11. Description of recommended non-thermal mixed waste treatment technologies: Version 1.0

    SciTech Connect (OSTI)

    NONE

    1995-08-01T23:59:59.000Z

    This document contains description of the technologies selected for inclusions in the Integrated Nonthermal Treatment Systems (INTS) Study. The purpose of these descriptions is to provide a more complete description of the INTS technologies. It supplements the summary descriptions of candidate nonthermal technologies that were considered for the INTS.

  12. THE SUCCESSFUL UTILIZATION OF COMMERCIAL TREATMENT CAPABILITIES TO DISPOSITION HANFORD NO-PATH-FORWARD SUSPECT TRANSURANIC WASTES

    SciTech Connect (OSTI)

    BLACKFORD LT; CATLOW RL; WEST LD; COLLINS MS; ROMINE LD; MOAK DJ

    2012-01-30T23:59:59.000Z

    The U.S. Department of Energy (DOE) Richland Operations Office (RL) has adopted the 2015 Vision for Cleanup of the Hanford Site. The CH2M HILL Plateau Remediation Company's (CHPRC) Waste and Fuels Management Project (W&FMP) and their partners support this mission by providing centralized waste management services for the Hanford Site waste generating organizations. At the time of the CHPRC contract award (August 2008) slightly more than 9,000 cubic meters (m{sup 3}) of legacy waste was defined as ''no-path-forward waste.'' A significant portion of this waste (7,650 m{sup 3}) comprised wastes with up to 50 grams of special nuclear materials (SNM) in oversized packages recovered during retrieval operations and large glove boxes removed from Hanford's Plutonium Finishing Plant (PFP). Through a collaborative effort between the DOE, CHPRC, and Perma-Fix Environmental Services, Inc. (PESI), pathways for these problematic wastes were developed and are currently being implemented.

  13. Radionuclide Retention Mechanisms in Secondary Waste-Form Testing: Phase II

    SciTech Connect (OSTI)

    Um, Wooyong; Valenta, Michelle M.; Chung, Chul-Woo; Yang, Jungseok; Engelhard, Mark H.; Serne, R. Jeffrey; Parker, Kent E.; Wang, Guohui; Cantrell, Kirk J.; Westsik, Joseph H.

    2011-09-26T23:59:59.000Z

    This report describes the results from laboratory tests performed at Pacific Northwest National Laboratory (PNNL) for Washington River Protection Solutions (WRPS) to evaluate candidate stabilization technologies that have the potential to successfully treat liquid secondary waste stream effluents produced by the Hanford Tank Waste Treatment and Immobilization Plant (WTP). WRPS is considering the design and construction of a Solidification Treatment Unit (STU) for the Effluent Treatment Facility (ETF) at Hanford. The ETF, a multi-waste, treatment-and-storage unit that has been permitted under the Resource Conservation and Recovery Act (RCRA), can accept dangerous, low-level, and mixed wastewaters for treatment. The STU needs to be operational by 2018 to receive secondary liquid waste generated during operation of the WTP. The STU will provide the additional capacity needed for ETF to process the increased volume of secondary waste expected to be produced by WTP. This report on radionuclide retention mechanisms describes the testing and characterization results that improve understanding of radionuclide retention mechanisms, especially for pertechnetate, {sup 99}TcO{sub 4}{sup -} in four different waste forms: Cast Stone, DuraLith alkali aluminosilicate geopolymer, encapsulated fluidized bed steam reforming (FBSR) product, and Ceramicrete phosphate bonded ceramic. These data and results will be used to fill existing data gaps on the candidate technologies to support a decision-making process that will identify a subset of the candidate waste forms that are most promising and should undergo further performance testing.

  14. The Department of Energy's $12.2 Billion Waste Treatment and Immobilization Plant - Quality Assurance Issues

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual Siteof Energy 2, 2015 - JanuaryTank 48H TreatmentEnergyEnergy

  15. WRPS MEETING THE CHALLENGE OF TANK WASTE

    SciTech Connect (OSTI)

    BRITTON JC

    2012-02-21T23:59:59.000Z

    Washington River Protection Solutions (WRPS) is the Hanford tank operations contractor, charged with managing one of the most challenging environmental cleanup projects in the nation. The U.S. Department of Energy hired WRPS to manage 56 million gallons of high-level radioactive waste stored in 177 underground tanks. The waste is the legacy of 45 years of plutonium production for the U. S. nuclear arsenal. WRPS mission is three-fold: safely manage the waste until it can be processed and immobilized; develop the tools and techniques to retrieve the waste from the tanks, and build the infrastructure needed to deliver the waste to the Waste Treatment Plant (WTP) when it begins operating. WTP will 'vitrify' the waste by mixing it with silica and other materials and heating it in an electric melter. Vitrification turns the waste into a sturdy glass that will isolate the radioactivity from the environment. It will take more than 20 years to process all the tank waste. The tank waste is a complex highly radioactive mixture of liquid, sludge and solids. The radioactivity, chemical composition of the waste and the limited access to the underground storage tanks makes retrieval a challenge. Waste is being retrieved from aging single-shell tanks and transferred to newer, safer double-shell tanks. WRPS is using a new technology known as enhanced-reach sluicing to remove waste. A high-pressure stream of liquid is sprayed at 100 gallons per minute through a telescoping arm onto a hard waste layer several inches thick covering the waste. The waste is broken up, moved to a central pump suction and removed from the tank. The innovative Mobile Arm Retrieval System (MARS) is also being used to retrieve waste. MARS is a remotely operated, telescoping arm installed on a mast in the center of the tank. It uses multiple technologies to scrape, scour and rake the waste toward a pump for removal. The American Reinvestment and Recovery Act (ARRA) provided nearly $326 million over two-and-a-half years to modernize the infrastructure in Hanford's tank farms. WRPS issued 850 subcontracts totaling more than $152 million with nearly 76 percent of that total awarded to small businesses. WRPS used the funding to upgrade tank farm infrastructure, develop technologies to retrieve and consolidate tank waste and extend the life of two critical operating facilities needed to feed waste to the WTP. The 222-S Laboratory analyzes waste to support waste retrievals and transfers. The laboratory was upgraded to support future WTP operations with a new computer system, new analytical equipment, a new office building and a new climate-controlled warehouse. The 242-A Evaporator was upgraded with a control-room simulator for operator training and several upgrades to aging equipment. The facility is used to remove liquid from the tank waste, creating additional storage space, necessary for continued waste retrievals and WTP operation. The One System Integrated Project Team is ajoint effort ofWRPS and Bechtel National to identify and resolve common issues associated with commissioning, feeding and operating the Waste Treatment Plant. Two new facilities are being designed to support WTP hot commlsslomng. The Interim Hanford Storage project is planned to store canisters of immobilized high-level radioactive waste glass produced by the vitrification plant. The facility will use open racks to store the 15-foot long, two-foot diameter canisters of waste, which require remote handling. The Secondary Liquid Waste Treatment Project is a major upgrade to the existing Effluent Treatment Facility at Hanford so it can treat about 10 million gallons of liquid radioactive and hazardous effluent a year from the vitrification plant. The One System approach brings the staff of both companies together to identify and resolve WTP safety issues. A questioning attitude is encouraged and an open forum is maintained for employees to raise issues. WRPS is completing its mission safely with record-setting safety performance. Since WRPS took over the Hanford Tank Operations Contract in October 2

  16. Hazardous Waste Management (Oklahoma)

    Broader source: Energy.gov [DOE]

    This article states regulations for the disposal of hazardous waste. It also provides information about permit requirements for the transport, treatment and storage of such waste. It also mentions...

  17. Guidelines for mixed waste minimization

    SciTech Connect (OSTI)

    Owens, C.

    1992-02-01T23:59:59.000Z

    Currently, there is no commercial mixed waste disposal available in the United States. Storage and treatment for commercial mixed waste is limited. Host States and compacts region officials are encouraging their mixed waste generators to minimize their mixed wastes because of management limitations. This document provides a guide to mixed waste minimization.

  18. Radioactive Waste Management Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1999-07-09T23:59:59.000Z

    This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. Change 1 dated 6/19/01 removes the requirement that Headquarters is to be notified and the Office of Environment, Safety and Health consulted for exemptions for use of non-DOE treatment facilities. Certified 1-9-07.

  19. LFCM (liquid-fed ceramic melter) vitrification technology: Quarterly progress report, January--March 1987

    SciTech Connect (OSTI)

    Brouns, R. A.; Allen, C. R.; Powell, J. A. (comps.)

    1988-05-01T23:59:59.000Z

    This report is compiled by the Nuclear Waste Treatment Program and the Hanford Waste Vitrification Program at Pacific Northwest Laboratory to describe the progress in developing, testing, applying and documenting liquid-fed ceramic melter vitrification technology. Progress in the following technical subject areas during the second quarter of FY 1987 is discussed: melting process chemistry and glass development, feed preparation and transfer systems, melter systems, canister filling and handling systems, and process/product modeling. 23 refs., 14 figs., 10 tabs.

  20. LFCM (liquid-fed ceramic melter) vitrification technology: Quarterly progress report, April-June 1986

    SciTech Connect (OSTI)

    Burkholder, H.C.; Allen, C.R. (comps.)

    1987-02-01T23:59:59.000Z

    This report is compiled by the Nuclear Waste Treatment Program and the Hanford Waste Vitrification Program at Pacific Northwest Laboratory to document progress on liquid-fed ceramic melter (LFCM) vitrification technology. Progress in the following technical subject areas during the third quarter of FY 1986 is discussed: melting process chemistry and glass development, feed preparation and transfer systems, melter systems, canister filling and handling systems, off-gas systems, and process/product modeling and control.

  1. Implementation of Recommendations from the One System Comparative Evaluation of the Hanford Tank Farms and Waste Treatment Plant Safety Bases

    SciTech Connect (OSTI)

    Garrett, Richard L. [Washington River Protection Systems, Richland, WA (United States); Niemi, Belinda J. [Washington River Protection Systems, Richland, WA (United States); Paik, Ingle K. [Washington River Protection Systems, Richland, WA (United States); Buczek, Jeffrey A. [AREVA Federal Services LLC (United States); Lietzow, J. [URS Professional Services (United States); McCoy, F. [AREVA Federal Services LLC (United States); Beranek, F. [URS Professional Services (United States); Gupta, M. [URS Professional Services (United States)

    2013-11-07T23:59:59.000Z

    A Comparative Evaluation was conducted for One System Integrated Project Team to compare the safety bases for the Hanford Waste Treatment and Immobilization Plant Project (WTP) and Tank Operations Contract (TOC) (i.e., Tank Farms) by an Expert Review Team. The evaluation had an overarching purpose to facilitate effective integration between WTP and TOC safety bases. It was to provide One System management with an objective evaluation of identified differences in safety basis process requirements, guidance, direction, procedures, and products (including safety controls, key safety basis inputs and assumptions, and consequence calculation methodologies) between WTP and TOC. The evaluation identified 25 recommendations (Opportunities for Integration). The resolution of these recommendations resulted in 16 implementation plans. The completion of these implementation plans will help ensure consistent safety bases for WTP and TOC along with consistent safety basis processes. procedures, and analyses. and should increase the likelihood of a successful startup of the WTP. This early integration will result in long-term cost savings and significant operational improvements. In addition, the implementation plans lead to the development of eight new safety analysis methodologies that can be used at other U.S. Department of Energy (US DOE) complex sites where URS Corporation is involved.

  2. Prospects for pyrolysis technologies in managing municipal, industrial, and DOE cleanup wastes

    SciTech Connect (OSTI)

    Reaven, S.J. [State Univ. of New York, Stony Brook, NY (United States)

    1994-12-01T23:59:59.000Z

    Pyrolysis converts portions of municipal solid wastes, hazardous wastes, and special wastes such as tires, medical wastes, and even old landfills into solid carbon and a liquid or gaseous hydrocarbon stream. Pyrolysis heats a carbonaceous waste stream typically to 290--900 C in the absence of oxygen, and reduces the volume of waste by 90% and its weight by 75%. The solid carbon char has existing markets as an ingredient in many manufactured goods, and as an adsorbent or filter to sequester certain hazardous wastes. Pyrolytic gases may be burned as fuel by utilities, or liquefied for use as chemical feedstocks, or low-pollution motor vehicle fuels and fuel additives. This report analyzes the potential applications of pyrolysis in the Long Island region and evaluates for the four most promising pyrolytic systems their technological and commercial readiness, their applicability to regional waste management needs, and their conformity with DOE requirements for environmental restoration and waste management. This summary characterizes their engineering performance, environmental effects, costs, product applications, and markets. Because it can effectively treat those wastes that are inadequately addressed by current systems, pyrolysis can play an important complementing role in the region`s existing waste management strategy. Its role could be even more significant if the region moves away from existing commitments to incineration and MSW composting. Either way, Long Island could become the center for a pyrolysis-based recovery services industry serving global markets in municipal solid waste treatment and hazardous waste cleanup. 162 refs.

  3. SYNTHESIS OF SULFUR-BASED WATER TREATMENT AGENT FROM SULFUR DIOXIDE WASTE STREAMS

    SciTech Connect (OSTI)

    Robert C. Brown; Maohong Fan

    2001-12-01T23:59:59.000Z

    We propose a process that uses sulfur dioxide from coal combustion as a raw material to synthesize polymeric ferric sulfate (PFS), a water treatment agent. The process uses sodium chlorate as an oxidant and ferrous sulfate as an absorbent. The major chemical mechanisms in this reaction system include oxidation, hydrolysis, and polymerization. Oxidation determines sulfur conversion efficiency while hydrolysis and polymerization control the quality of product. Many factors, including SO{sub 2} inlet concentration, flow rate of simulated flue gas, reaction temperature, addition rate of oxidant and stirring rate, may affect the efficiencies of SO{sub 2} removal. Currently, the effects of SO{sub 2} inlet concentration, the flow rate of simulated flue gas and addition rate of flue gas on removal efficiencies of SO{sub 2}, are being investigated. Experiments shown in this report have demonstrated that the conversion efficiencies of sulfur dioxide with ferrous sulfate as an absorbent are in the range of 60-80% under the adopted process conditions. However, the conversion efficiency of sulfur dioxide may be improved by optimizing reaction conditions to be investigated. Partial quality indices of the synthesized products, including Fe{sup 2+} concentration and total iron concentration, have been evaluated.

  4. CERTIFICATION DOCKET FOR THE F0RhqE.R SITE OF THE RADIOACTIVE LIQUID WASTE TREATMENT PLANT (TA-45)

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group currentBradleyTableSelling7111A Lithologic and MonitorBayoBuffalo,/

  5. Completion report for the Inactive Liquid Low-Level Waste Tank Remediation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    NONE

    1996-02-01T23:59:59.000Z

    This report documents the results of the Inactive Liquid Low-Level Waste Tank Remediation Project at Oak Ridge National Laboratory (ORNL). The work performed is compared with that proposed in the statement of work and the service contract specification for the maintenance action to remediate tanks 3013, 3004-B, T-30, and 3001-B. The Federal Facility Agreement (FFA) among the U.S. Environmental Protection Agency (EPA), the Tennessee Department of Environment and Conservation (TDEC), and the U.S. Department of Energy (DOE) requires that all tanks, which have been removed from service and are designated in the FFA as Category D, must be remediated in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requirements. The Environmental Restoration Program`s inactive tank removal program strategy and plans for remediating the inactive LLLW tanks were documented in a report issued in January 1995 (Inactive Tanks Remediation Program Strategy and Plans for Oak Ridge National Laboratory, Oak Ridge, Tennessee, ORNL/ER-297). The inactive (Category D) tanks were initially screened for remediation according to risk, remediation technology required, level of instrumentation available, interferences with other piping and equipment, location, and available sludge removal techniques and storage requirements. On the basis of this preliminary screening, the tanks were assigned to one of five batches (I through V) for consideration of remedial action alternatives, and these batches were tentatively scheduled for remedial actions. The eight links tentatively assigned to Batch I were divided into two groups (Series I and Series II).

  6. EM Makes Significant Progress on Dispositioning Transuranic Waste...

    Office of Environmental Management (EM)

    Addthis Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. Workers treat sludge-bearing, transuranic waste from the Advanced Mixed...

  7. Nuclear waste treatment - Studying the mixed ion type effects and concentration on the behaviour of oxide dispersions

    SciTech Connect (OSTI)

    Omokanye, Qanitalillahi; Biggs, Simon [Institute of Particle Science and Engineering, University of Leeds, Leeds LS2 9JT (United Kingdom)

    2007-07-01T23:59:59.000Z

    In order to gain good control over a particulate dispersion it is necessary to accurately characterise the strength of inter-particle forces that may be operating. Such control is not routinely used, as yet, in the nuclear industry despite the possible benefits. We are investigating the impact of mixed electrolyte systems, for example NaCl and Na{sub 2}SO{sub 4}, on the stability of oxide simulant particle dispersions. The electro-acoustic zeta potentials and shear yield stresses for concentrated dispersions have been measured across a range of pH conditions and electrolyte concentrations (0.001 M - 1.0 M). This paper summarizes initial data from these studies showing how the shear yield stress of concentrated aqueous oxide particle dispersions, can be adjusted through regulation of pH and the addition of background electrolytes (salt). The yield stress as a function of pH for these dispersions in mixed electrolytes showed a direct correlation with corresponding measurements of the zeta potential. Changes in the background electrolyte concentration or type were seen to cause a shift in the position of the isoelectric point (iep). Measurements of the shear yield stress showed a maximum at the iep corresponding to the position of maximum instability in the suspension. The consequences of these data for the efficient treatment of solid-liquid systems will be discussed. (authors)

  8. State Waste Discharge Permit application, 100-N Sewage Lagoon

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    As part of the Hanford Federal Facility Agreement and Consent Order negotiations (Ecology et al. 1994), the US Department of Energy, Richland Operations Office, the US Environmental Protection Agency, and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground on the Hanford Site which affect groundwater or have the potential to affect groundwater would be subject to permitting under the structure of Chapter 173--216 (or 173--218 where applicable) of the Washington Administrative Code, the State Waste Discharge Permit Program. As a result of this decision, the Washington State Department of Ecology and the US Department of Energy, Richland Operations Office entered into Consent Order No. DE 91NM-177, (Ecology and DOE-RL 1991). This document constitutes the State Waste Discharge Permit application for the 100-N Sewage Lagoon. Since the influent to the sewer lagoon is domestic waste water, the State Waste Discharge Permit application for Public Owned Treatment Works Discharges to Land was used. Although the 100-N Sewage Lagoon is not a Public Owned Treatment Works, the Public Owned Treatment Works application is more applicable than the application for industrial waste water. The 100-N Sewage Lagoon serves the 100-N Area and other Hanford Site areas by receiving domestic waste from two sources. A network of sanitary sewer piping and lift stations transfers domestic waste water from the 100-N Area buildings directly to the 100-N Sewage Lagoon. Waste is also received by trucks that transport domestic waste pumped from on site septic tanks and holding tanks. Three ponds comprise the 100-N Sewage Lagoon treatment system. These include a lined aeration pond and stabilization pond, as well as an unlined infiltration pond. Both piped-in and trucked-in domestic waste is discharged directly into the aeration pond.

  9. Idaho High-Level Waste & Facilities Disposition, Final Environmental Impact Statement

    SciTech Connect (OSTI)

    N /A

    2002-10-11T23:59:59.000Z

    This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. After considering comments on the Draft EIS (DOE/EIS-0287D), as well as information on available treatment technologies, DOE and the State of Idaho have identified separate preferred alternatives for waste treatment. DOE's preferred alternative for waste treatment is performance based with the focus on placing the wastes in forms suitable for disposal. Technologies available to meet the performance objectives may be chosen from the action alternatives analyzed in this EIS. The State of Idaho's Preferred Alternative for treating mixed transuranic waste/SBW and calcine is vitrification, with or without calcine separations. Under both the DOE and State of Idaho preferred alternatives, newly generated liquid waste would be segregated after 2005, stored or treated directly and disposed of as low-level, mixed low-level, or transuranic waste depending on its characteristics. The objective of each preferred alternative is to enable compliance with the legal requirement to have INEEL HLW road ready by a target date of 2035. Both DOE and the State of Idaho have identified the same preferred alternative for facilities disposition, which is to use performance-based closure methods for existing facilities and to design new facilities consistent with clean closure methods.

  10. Liquid heat capacity lasers

    DOE Patents [OSTI]

    Comaskey, Brian J. (Walnut Creek, CA); Scheibner, Karl F. (Tracy, CA); Ault, Earl R. (Livermore, CA)

    2007-05-01T23:59:59.000Z

    The heat capacity laser concept is extended to systems in which the heat capacity lasing media is a liquid. The laser active liquid is circulated from a reservoir (where the bulk of the media and hence waste heat resides) through a channel so configured for both optical pumping of the media for gain and for light amplification from the resulting gain.

  11. Waste Minimization Policy at the Romanian Nuclear Power Plant

    SciTech Connect (OSTI)

    Andrei, V.; Daian, I.

    2002-02-26T23:59:59.000Z

    The radioactive waste management system at Cernavoda Nuclear Power Plant (NPP) in Romania was designed to maintain acceptable levels of safety for workers and to protect human health and the environment from exposure to unacceptable levels of radiation. In accordance with terminology of the International Atomic Energy Agency (IAEA), this system consists of the ''pretreatment'' of solid and organic liquid radioactive waste, which may include part or all of the following activities: collection, handling, volume reduction (by an in-drum compactor, if appropriate), and storage. Gaseous and aqueous liquid wastes are managed according to the ''dilute and discharge'' strategy. Taking into account the fact that treatment/conditioning and disposal technologies are still not established, waste minimization at the source is a priority environmental management objective, while waste minimization at the disposal stage is presently just a theoretical requirement for future adopted technologies . The necessary operational and maintenance procedures are in place at Cernavoda to minimize the production and contamination of waste. Administrative and technical measures are established to minimize waste volumes. Thus, an annual environmental target of a maximum 30 m3 of radioactive waste volume arising from operation and maintenance has been established. Within the first five years of operations at Cernavoda NPP, this target has been met. The successful implementation of the waste minimization policy has been accompanied by a cost reduction while the occupational doses for plant workers have been maintained at as low as reasonably practicable levels. This paper will describe key features of the waste management system along with the actual experience that has been realized with respect to minimizing the waste volumes at the Cernavoda NPP.

  12. HANFORD SITE RIVER PROTECTION PROJECT (RPP) TRANSURANIC (TRU) TANK WASTE IDENTIFICATION & PLANNING FOR REVRIEVAL TREATMENT & EVENTUAL DISPOSAL AT WIPP

    SciTech Connect (OSTI)

    KRISTOFZSKI, J.G.; TEDESCHI, R.; JOHNSON, M.E.; JENNINGS, M

    2006-01-18T23:59:59.000Z

    The CH2M HILL Manford Group, Inc. (CHG) conducts business to achieve the goals of the Office of River Protection (ORP) at Hanford. As an employee owned company, CHG employees have a strong motivation to develop innovative solutions to enhance project and company performance while ensuring protection of human health and the environment. CHG is responsible to manage and perform work required to safely store, enhance readiness for waste feed delivery, and prepare for treated waste receipts for the approximately 53 million gallons of legacy mixed radioactive waste currently at the Hanford Site tank farms. Safety and environmental awareness is integrated into all activities and work is accomplished in a manner that achieves high levels of quality while protecting the environment and the safety and health of workers and the public. This paper focuses on the innovative strategy to identify, retrieve, treat, and dispose of Hanford Transuranic (TRU) tank waste at the Waste Isolation Pilot Plant (WIPP).

  13. Microwave Technology for Waste Management Applications Including Disposition of Electronic Circuitry

    SciTech Connect (OSTI)

    Wicks, G.G. [Westinghouse Savannah River Company, AIKEN, SC (United States); Clark, D.E. [University of Florida, Gainesville, FL (United States); Schulz, R.L. [University of Flordia, Gainesville, FL (United States)

    1998-06-01T23:59:59.000Z

    Advanced microwave technology is being developed nationally and internationally for a variety of waste management and environmental remediation purposes. These efforts include treatment and destruction of a vast array of gaseous, liquid and solid hazardous wastes as well as subsequent immobilization of hazardous components into leach resistant forms. Microwave technology provides an important contribution to an arsenal of existing remediation methods that are designed to protect the public and environment from the undesirable consequences of hazardous materials. One application of special interest is the treatment of discarded electronic circuitry using a new hybrid microwave treatment process and subsequent reclamation of the precious metals within.

  14. Treatment of Radioactive Metallic Waste from Operation of Nuclear Power Plants by Melting - The German Way for a Consistent Recycling to Minimize the Quantity of Radioactive Waste from Operation and Dismantling for Disposal - 12016

    SciTech Connect (OSTI)

    Wegener, Dirk [GNS Gesellschaft fuer Nuklear-Service mbH, Essen (Germany); Kluth, Thomas [Siempelkamp Nukleartechnik GmbH, Krefeld (Germany)

    2012-07-01T23:59:59.000Z

    During maintenance of nuclear power plants, and during their decommissioning period, a large quantity of radioactive metallic waste will accrue. On the other hand the capacity for final disposal of radioactive waste in Germany is limited as well as that in the US. That is why all procedures related to this topic should be handled with a maximum of efficiency. The German model of consistent recycling of the radioactive metal scrap within the nuclear industry therefore also offers high capabilities for facilities in the US. The paper gives a compact overview of the impressive results of melting treatment, the current potential and further developments. Thousands of cubic metres of final disposal capacity have been saved. The highest level of efficiency and safety by combining general surface decontamination by blasting and nuclide specific decontamination by melting associated with the typical effects of homogenization. An established process - nationally and internationally recognized. Excellent connection between economy and ecology. (authors)

  15. Radioactive waste disposal package

    DOE Patents [OSTI]

    Lampe, Robert F. (Bethel Park, PA)

    1986-01-01T23:59:59.000Z

    A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

  16. Radioactive mixed waste disposal

    SciTech Connect (OSTI)

    Jasen, W.G.; Erpenbeck, E.G.

    1993-02-01T23:59:59.000Z

    Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA), the Resource Conservation and Recovery Act of 1976 (RCRA), and the Hazardous and Solid Waste Amendments (HSWA) have led to the definition of radioactive mixed wastes (RMW). The radioactive and hazardous properties of these wastes have resulted in the initiation of special projects for the management of these wastes. Other solid wastes at the Hanford Site include low-level wastes, transuranic (TRU), and nonradioactive hazardous wastes. This paper describes a system for the treatment, storage, and disposal (TSD) of solid radioactive waste.

  17. Report of exploratory trenching for the Decontamination and Waste Treatment Facility at Lawrence Livermore National Laboratory, Livermore, California

    SciTech Connect (OSTI)

    Dresen, M.D.; Weiss, R.B.

    1985-12-01T23:59:59.000Z

    Three exploratory trenches, totaling about 1,300 ft in length were excavated and logged across the site of a proposed Decontamination and Waste Treatment Facility (DWTF), to assess whether or not active Greenville fault zone, located about 4100 ft to the northeast, pass through or within 200 ft of the site. The layout of the trenches (12-16 ft deep) was designed to provide continuous coverage across the DWTF site and an area within 200 ft northeast and southwest of the site. Deposits exposed in the trench walls are primarily of clay, and are typical of weakly cemented silty sand to sandy silt with the alluvial deposits in the area. Several stream channels were encountered that appear to have an approximated east-west orintation. The channel deposits consist of well-sorted, medium to coarse-grained sand and gravel. A well-developed surface soil is laterally continuous across all three trenches. The soil reportedly formed during late Pleistocene time (about 35,000 to 40,000 yr before present) based on soil stratigraphic analyses. A moderately to well-developed buried soil is laterally continuous in all three trenches, except locally where it has been removed by channelling. This buried soil apparently formed about 100,000 yr before present. At least one older, discontinuous soil is present below the 100,000-yr-old soil in some locations. The age of the older soil is unknown. At several locations, two discontinuous buried soils were observed between the surface soil and the 100,000-yr-old soil. Various overlapping stratigraphic units could be traced across the trenches providing a continuous datum of at least 100,000 yr to assess the presence or absence of faulting. The continuity of stratigraphic units in all the trenches demonstrated that no active faults pass through or within 200 ft of the proposed DWTF site.

  18. International Best Practices for Pre-Processing and Co-Processing Municipal Solid Waste and Sewage Sludge in the Cement Industry

    E-Print Network [OSTI]

    Hasanbeigi, Ali

    2013-01-01T23:59:59.000Z

    linking municipal solid waste treatment facilities as wellReview of Municipal Solid Waste Thermal Treatment Practices.Biological Treatment of Municipal Solid Waste. Available at

  19. Resource Management Plan for the US Department of Energy Oak Ridge Reservation. Volume 15, Appendix P: waste management

    SciTech Connect (OSTI)

    Kelly, B.A.

    1984-07-01T23:59:59.000Z

    Since their inception, the DOE facilities on the Oak Ridge Reservation have been the source of a variety of airborne, liquid, and solid wastes which are characterized as nonhazardous, hazardous, and/or radioactive. The major airborne releases come from three primary sources: steam plant emissions, process discharge, and cooling towers. Liquid wastes are handled in various manners depending upon the particular waste, but in general, major corrosive waste streams are neutralized prior to discharge with the discharge routed to holding or settling ponds. The major solid wastes are derived from construction debris, sanitary operation, and radioactive processes, and the machining operations at Y-12. Nonradioactive hazardous wastes are disposed in solid waste storage areas, shipped to commercial disposal facilities, returned in sludge ponds, or sent to radioactive waste burial areas. The radioactive-hazardous wastes are treated in two manners: storage of the waste until acceptable disposal options are developed, or treatment of the waste to remove or destroy one of the components prior to disposal. 5 references, 4 figures, 13 tables.

  20. The effect of chemical composition on the PCT durability of mixed waste glasses from wastewater treatment sludges

    SciTech Connect (OSTI)

    Resce, J.L.; Ragsdale, R.G.; Overcamp, T.J. [Clemson Univ., SC (United States); Bickford, D.F.; Cicero, C.A. [Savannah River Technology Center, Aiken, SC (United States)

    1995-01-25T23:59:59.000Z

    An experimental program has been designed to examine the chemical durability of glass compositions derived from the vitrification of simulated wastewater treatment sludges. These sludges represent the majority of low-level mixed wastes currently in need of treatment by the US DOE. The major oxides in these model glasses included SiO{sub 2}, Al{sub 2}O{sub 3}, B{sub 2}O{sub 3}, Na{sub 2}O, CaO and Fe{sub 2}O{sub 3}. In addition, three minor oxides, BaO, NiO, and PbO, were added as hazardous metals. The major oxides were each varied at two levels resulting in 32 experimental glasses. The chemical durability was measured by the 7-Day Product Consistency Test (PCT). The normalized sodium release rates (NRR{sub Na}) of these glasses ranged from 0.01 to 4.99 g/m{sup 2}. The molar ratio of the glass-former to glass-modifier (F/M) was found to have the greatest effect on PCT durability. Glass-formers included SiO{sub 2}, Al{sub 2}O{sub 3}, and B{sub 2}O{sub 3}, while Na{sub 2}O, CaO, BaO, NiO, and PbO were glass-modifiers. As this ratio increased from 0.75 to 2.0, NRR{sub Na} was found to decrease between one and two orders of magnitude. Another important effect on NRR{sub Na} was the Na{sub 2}O/CaO ratio. As this ratio increased from 0.5 to 2.0, NRR{sub Na} increased up to two orders of magnitude for the glasses with the low F/M ratio but almost no effect was observed for the glasses with the high F/M ratio. Increasing the iron oxide content from 2 to 18 mole% was found to decrease NRR{sub Na} one order of magnitude for the glasses with low F/M but iron had little effect on the glasses with the high F/M ratio. The durability also increased when 10 mole percent Al{sub 2}O{sub 3} was included in low iron oxide glasses but no effect was observed with the high iron glasses. The addition of B{sub 2}O{sub 3} had little effect on durability. The effects of other composition parameters on durability are discussed as well.