National Library of Energy BETA

Sample records for integrated waste treatment

  1. Overview of Integrated Waste Treatment Unit

    Office of Environmental Management (EM)

    Environmental Management Integrated Waste Treatment Unit Overview Overview for the DOE High Level Waste Corporate Board March 5, 2009 safety performance cleanup closure...

  2. Hanford Site waste treatment/storage/disposal integration

    SciTech Connect (OSTI)

    MCDONALD, K.M.

    1999-02-24

    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.

  3. Integrated Waste Treatment Unit GFSI Risk Management Plan

    SciTech Connect (OSTI)

    W. A. Owca

    2007-06-21

    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).

  4. Integrated Waste Treatment Facility Fact Sheet | Department of Energy

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy A plug-inPPLforLDRDEnergy Copyrights ASite InspectionDepartmentTrainingWaste

  5. 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)

    2012-12-20

    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.

  6. Independent Oversight Review, Sodium Bearing Waste Treatment...

    Office of Environmental Management (EM)

    2012 Review of the Sodium Bearing Waste Treatment Project - Integrated Waste Treatment Unit Federal Operational Readiness Review This report documents the results of an...

  7. Independent Oversight Review, Sodium Bearing Waste Treatment...

    Office of Environmental Management (EM)

    2012 Review of the Sodium Bearing Waste Treatment Project - Integrated Waste Treatment Unit Contractor Operational Readiness Review This report documents the results of an...

  8. TREATMENT SYSTEMS AN INTEGRATED APPROACH

    E-Print Network [OSTI]

    for on-site management and treatment of effluent and solid waste 3. Provide for surface water attenuationECOLOGICAL TREATMENT SYSTEMS AN INTEGRATED APPROACH TO THE TREATMENT OF WASTE AND WASTE WATER In nature there is no waste, because the waste of one organism is food for another Inherent

  9. Waste treatment capacity of raft hydroponic lettuce production in an integrated fish culture system and the contribution of lettuce to treatment capacity 

    E-Print Network [OSTI]

    Gloger, Kelly C

    1995-01-01

    Two experiments were conducted to determine: 1.) the waste treatment capacity of raft hydroponic lettuce production in an integrated fish culture system and 2.) the contribution of lettuce plants, Lactuca saliva, cv. Paris ...

  10. 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...

  11. One System Integrated Project Team Progress in Coordinating Hanford Tank Farms and the Waste Treatment Plant

    SciTech Connect (OSTI)

    Skwarek, Raymond J.; Harp, Ben J.; Duncan, Garth M.

    2013-12-18

    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.

  12. Integrated chemical/biological treatment of paint stripper mixed waste: Metals toxicity and separation

    SciTech Connect (OSTI)

    Vanderberg-Twary, L.; Grumbine, R.K.; Foreman, T.; Hanners, J.L.; Brainard, J.R.; Sauer, N.N.; Unkefer, P.J.

    1995-05-01

    The DOE complex has generated vast quantities of complex heterogeneous mixed wastes. Paint stripper waste (PSW) is a complex waste that arose from decontamination and decommissioning activities. It contains paint stripper, cheesecloth, cellulose-based paints with Pb and Cr, and suspect Pu. Los Alamos National Laboratory has 150--200 barrels of PSW and other national laboratories such as Rocky Flats Plant have many more barrels of heterogeneous waste. Few technologies exist that can treat this complex waste. Our approach to solving this problem is the integration of two established technologies: biodegradation and metals chelation.

  13. Integrated Waste Treatment Unit (IWTU) Input Coal Analyses and Off-Gass Filter (OGF) Content Analyses

    SciTech Connect (OSTI)

    Jantzen, Carol M.; Missimer, David M.; Guenther, Chris P.; Shekhawat, Dushyant; VanEssendelft, Dirk T.; Means, Nicholas C.

    2015-04-23

    A full engineering scale Fluidized Bed Steam Reformer (FBSR) system is being used at the Idaho Nuclear Technology and Engineering Center (INTEC) to stabilize acidic Low Activity Waste (LAW) known as Sodium Bearing Waste (SBW). The INTEC facility, known as the Integrated Waste Treatment Unit (IWTU), underwent an Operational Readiness Review (ORR) and a Technology Readiness Assessment (TRA) in March 2014. The IWTU began non-radioactive simulant processing in late 2014 and by January, 2015 ; the IWTU had processed 62,000 gallons of simulant. The facility is currently in a planned outage for inspection of the equipment and will resume processing simulated waste feed before commencing to process 900,000 gallons of radioactive SBW. The SBW acidic waste will be made into a granular FBSR product (carbonate based) for disposal in the Waste Isolation Pilot Plant (WIPP). In the FBSR process calcined coal is used to create a CO2 fugacity to force the waste species to convert to carbonate species. The quality of the coal, which is a feed input, is important because the reactivity, moisture, and volatiles (C,H,N,O, and S) in the coal impact the reactions and control of the mineralizing process in the primary steam reforming vessel, the Denitration and Mineralizing Reformer (DMR). Too much moisture in the coal can require that additional coal be used. However since moisture in the coal is only a small fraction of the moisture from the fluidizing steam this can be self-correcting. If the coal reactivity or heating value is too low then the coal feedrate needs to be adjusted to achieve the desired heat generation. Too little coal and autothermal heat generation in the DMR cannot be sustained and/or the carbon dioxide fugacity will be too low to create the desired carbonate mineral species. Too much coal and excess S and hydroxide species can form. Excess sulfur from coal that (1) is too rich in sulfur or (2) from overfeeding coal can promote wall scale and contribute to corrosion in process piping and materials, in excessive off-gas absorbent loading, and in undesired process emissions. The ash content of the coal is important as the ash adds to the DMR and other vessel products which affect the final waste product mass and composition. The amount and composition of the ash also affects the reaction kinetics. Thus ash content and composition contributes to the mass balance. In addition, sodium, potassium, calcium, sulfur, and maybe silica and alumina in the ash may contribute to wall-scale formation. Sodium, potassium, and alumina in the ash will be overwhelmed by the sodium, potassium, and alumina from the feed but the impact from the other ash components needs to be quantified. A maximum coal particle size is specified so the feed system does not plug and a minimum particle size is specified to prevent excess elutriation from the DMR to the Process Gas Filter (PGF). A vendor specification was used to procure the calcined coal for IWTU processing. While the vendor supplied a composite analysis for the 22 tons of coal (Appendix A), this study compares independent analyses of the coal performed at the Savannah River National Laboratory (SRNL) and at the National Energy Technology Laboratory (NETL). Three supersacks a were sampled at three different heights within the sack in order to determine within bag variability and between bag variability of the coal. These analyses were also compared to the vendor’s composite analyses and to the coal specification. These analyses were also compared to historic data on Bestac coal analyses that had been performed at Hazen Research Inc. (HRI) between 2004-2011.

  14. Development of Site-Specific Soil Design Basis Earthquake (DBE) Parameters for the Integrated Waste Treatment Unit (IWTU)

    SciTech Connect (OSTI)

    Payne, Suzette

    2008-08-01

    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).

  15. 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)

    1997-01-01

    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.

  16. Hot waste-to-energy flue gas treatment using an integrated fluidised bed reactor

    SciTech Connect (OSTI)

    Bianchini, A.; Pellegrini, M. [DIEM, Department of Mechanical Engineering, Faculty of Engineering, University of Bologna, Viale Risorgimento 2, 40136 Bologna (Italy); Saccani, C. [DIEM, Department of Mechanical Engineering, Faculty of Engineering, University of Bologna, Viale Risorgimento 2, 40136 Bologna (Italy)], E-mail: cesare.saccani@unibo.it

    2009-04-15

    This paper describes an innovative process to increase superheated steam temperatures in waste-to-energy (WTE) plants. This solution is mainly characterised by a fluidised bed reactor in which hot flue gas is treated both chemically and mechanically. This approach, together with gas recirculation, increases the energy conversion efficiency, and raises the superheated steam temperature without decreasing the useful life of the superheater. This paper presents new experimental data obtained from the test facility installed at the Hera S.p.A. WTE plant in Forli, Italy; discusses changes that can be implemented to increase the duration of experimental testing; offers suggestions for the design of an industrial solution.

  17. Waste Treatment Plant - 12508

    SciTech Connect (OSTI)

    Harp, Benton; Olds, Erik

    2012-07-01

    The Waste Treatment Plant (WTP) will immobilize millions of gallons of Hanford's tank waste into solid glass using a proven technology called vitrification. The vitrification process will turn the waste into a stable glass form that is safe for long-term storage. Our discussion of the WTP will include a description of the ongoing design and construction of this large, complex, first-of-a-kind project. The concept for the operation of the WTP is to separate high-level and low-activity waste fractions, and immobilize those fractions in glass using vitrification. The WTP includes four major nuclear facilities and various support facilities. Waste from the Tank Farms is first pumped to the Pretreatment Facility at the WTP through an underground pipe-in-pipe system. When construction is complete, the Pretreatment Facility will be 12 stories high, 540 feet long and 215 feet wide, making it the largest of the four major nuclear facilities that compose the WTP. The total size of this facility will be more than 490,000 square feet. More than 8.2 million craft hours are required to construct this facility. Currently, the Pretreatment Facility is 51 percent complete. At the Pretreatment Facility the waste is pumped to the interior waste feed receipt vessels. Each of these four vessels is 55-feet tall and has a 375,000 gallon capacity, which makes them the largest vessels inside the Pretreatment Facility. These vessels contain a series of internal pulse-jet mixers to keep incoming waste properly mixed. The vessels are inside the black-cell areas, completely enclosed behind thick steel-laced, high strength concrete walls. The black cells are designed to be maintenance free with no moving parts. Once hot operations commence the black-cell area will be inaccessible. Surrounded by black cells, is the 'hot cell canyon'. The hot cell contains all the moving and replaceable components to remove solids and extract liquids. In this area, there is ultrafiltration equipment, cesium-ion exchange columns, evaporator boilers and recirculation pumps, and various mechanical process pumps for transferring process fluids. During the first phase of pretreatment, the waste will be concentrated using an evaporation process. Solids will be filtered out, and the remaining soluble, highly radioactive isotopes will be removed using an ion-exchange process. The high-level solids will be sent to the High-Level Waste (HLW) Vitrification Facility, and the low activity liquids will be sent to the Low-Activity Waste (LAW) Vitrification Facility for further processing. The high-level waste will be transferred via underground pipes to the HLW Facility from the Pretreatment Facility. The waste first arrives at the wet cell, which rests inside a black-cell area. The pretreated waste is transferred through shielded pipes into a series of melter preparation and feed vessels before reaching the melters. Liquids from various facility processes also return to the wet cell for interim storage before recycling back to the Pretreatment Facility. (authors)

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

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

    2015 Independent Oversight Activity Report, Hanford Waste Treatment and Immobilization Plant - October 2013 Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility...

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

    Office of Environmental Management (EM)

    2013 More Documents & Publications Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility Waste Treatment and Immobilization Plant (WTP) Analytical Laboratory...

  20. The Integrated Waste Tracking System - A Flexible Waste Management Tool

    SciTech Connect (OSTI)

    Anderson, Robert Stephen

    2001-02-01

    The US Department of Energy (DOE) Idaho National Engineering and Environmental Laboratory (INEEL) has fully embraced a flexible, computer-based tool to help increase waste management efficiency and integrate multiple operational functions from waste generation through waste disposition while reducing cost. The Integrated Waste Tracking System (IWTS)provides comprehensive information management for containerized waste during generation,storage, treatment, transport, and disposal. The IWTS provides all information necessary for facilities to properly manage and demonstrate regulatory compliance. As a platformindependent, client-server and Web-based inventory and compliance system, the IWTS has proven to be a successful tracking, characterization, compliance, and reporting tool that meets the needs of both operations and management while providing a high level of management flexibility.

  1. Tank Waste System Integrated Project Team

    Office of Environmental Management (EM)

    to protect human health, the environment and national security are maintained. Tank Waste System Tank Waste System Integrated Project Team Integrated Project Team Steve...

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

    Office of Environmental Management (EM)

    3 Independent Oversight Review, Waste Treatment and Immobilization Plant - March 2013 March 2013 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction...

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

    Office of Environmental Management (EM)

    2 Independent Oversight Review, Waste Treatment and Immobilization Plant - March 2012 March 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant Project...

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

    Office of Environmental Management (EM)

    August 2011 Independent Oversight Review, Waste Treatment and Immobilization Plant - August 2011 August 2011 Hanford Waste Treatment and Immobilization Plant Construction Quality...

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

    Office of Environmental Management (EM)

    October 2012 Independent Oversight Review, Waste Treatment and Immobilization Plant - October 2012 October 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant...

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

    Office of Environmental Management (EM)

    January 2013 Independent Oversight Review, Waste Treatment and Immobilization Plant - January 2013 January 2013 Review of the Hanford Waste Treatment and Immobilization Plant...

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

    Office of Environmental Management (EM)

    May 2013 Independent Oversight Review, Waste Treatment and Immobilization Plant - May 2013 May 2013 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction...

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

    Office of Environmental Management (EM)

    August 2012 Independent Oversight Review, Waste Treatment and Immobilization Plant - August 2012 August 2012 Review of the Hanford Site Waste Treatment and Immobilization Plant...

  9. 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...

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

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

    Advanced Mixed Waste Treatment Project - April 2013 Independent Oversight Review, Advanced Mixed Waste Treatment Project - April 2013 April 2013 Review of Radiation Protection...

  11. Waste Treatment Facility Passes Federal Inspection, Completes...

    Office of Environmental Management (EM)

    Waste Treatment Facility Passes Federal Inspection, Completes Final Milestone, Begins Startup Waste Treatment Facility Passes Federal Inspection, Completes Final Milestone, Begins...

  12. 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)

    2002-01-01

    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.

  13. Tunable, self-powered integrated arc plasma-melter vitrification system for waste treatment and resource recovery

    DOE Patents [OSTI]

    Titus, Charles H. (Newtown Square, PA); Cohn, Daniel R. (Chestnuthill, MA); Surma, Jeffrey E. (Kennewick, WA)

    1998-01-01

    The present invention provides a relatively compact self-powered, tunable waste conversion system and apparatus which has the advantage of highly robust operation which provides complete or substantially complete conversion of a wide range of waste streams into useful gas and a stable, nonleachable solid product at a single location with greatly reduced air pollution to meet air quality standards. The system provides the capability for highly efficient conversion of waste into high quality combustible gas and for high efficiency conversion of the gas into electricity by utilizing a high efficiency gas turbine or by an internal combustion engine. The solid product can be suitable for various commercial applications. Alternatively, the solid product stream, which is a safe, stable material, may be disposed of without special considerations as hazardous material. In the preferred embodiment of the invention, the arc plasma furnace and joule heated melter are formed as a fully integrated unit with a common melt pool having circuit arrangements for the simultaneous independently controllable operation of both the arc plasma and the joule heated portions of the unit without interference with one another. The preferred configuration of this embodiment of the invention utilizes two arc plasma electrodes with an elongated chamber for the molten pool such that the molten pool is capable of providing conducting paths between electrodes. The apparatus may additionally be employed with reduced or without further use of the gases generated by the conversion process. The apparatus may be employed as a self-powered or net electricity producing unit where use of an auxiliary fuel provides the required level of electricity production.

  14. Report: EM Tank Waste Subcommittee Full Report for Waste Treatment...

    Office of Environmental Management (EM)

    meeting, enclosed please find the Environmental Management Advisory Board EM Tank Waste Subcommittee Report for Waste Treatment Plant; Report Number EMAB EM-TWS WTP-001,...

  15. Waste Treatment and Immobilation Plant HLW Waste Vitrification...

    Office of Environmental Management (EM)

    6 Technology Readiness Assessment for the Waste Treatment and Immobilization Plant (WTP) HLW Waste Vitrification Facility L. Holton D. Alexander C. Babel H. Sutter J. Young August...

  16. Integrated Solid Waste Management Act (Nebraska)

    Broader source: Energy.gov [DOE]

    This act affirms the state's support for alternative waste management practices, including waste reduction and resource recovery. Each county and municipality is required to file an integrated...

  17. A perspective of hazardous waste and mixed waste treatment technology at the Savannah River Site

    SciTech Connect (OSTI)

    England, J.L.; Venkatesh, S.; Bailey, L.L.; Langton, C.A.; Hay, M.S.; Stevens, C.B.; Carroll, S.J.

    1991-12-31

    Treatment technologies for the preparation and treatment of heavy metal mixed wastes, contaminated soils, and mixed mercury wastes are being considered at the Savannah River Site (SRS), a DOE nuclear material processing facility operated by Westinghouse Savannah River Company (WSRC). The proposed treatment technologies to be included at the Hazardous Waste/Mixed Waste Treatment Building at SRS are based on the regulatory requirements, projected waste volumes, existing technology, cost effectiveness, and project schedule. Waste sorting and size reduction are the initial step in the treatment process. After sorting/size reduction the wastes would go to the next applicable treatment module. For solid heavy metal mixed wastes the proposed treatment is macroencapsulation using a thermoplastic polymer. This process reduces the leachability of hazardous constituents from the waste and allows easy verification of the coating integrity. Stabilization and solidification in a cement matrix will treat a wide variety of wastes (i.e. soils, decontamination water). Some pretreatments may be required (i.e. Ph adjustment) before stabilization. Other pretreatments such as soil washing can reduce the amount of waste to be stabilized. Radioactive contaminated mercury waste at the SRS comes in numerous forms (i.e. process equipment, soils, and lab waste) with the required treatment of high mercury wastes being roasting/retorting and recovery. Any unrecyclable radioactive contaminated elemental mercury would be amalgamated, utilizing a batch system, before disposal.

  18. A perspective of hazardous waste and mixed waste treatment technology at the Savannah River Site

    SciTech Connect (OSTI)

    England, J.L.; Venkatesh, S.; Bailey, L.L.; Langton, C.A.; Hay, M.S.; Stevens, C.B.; Carroll, S.J.

    1991-01-01

    Treatment technologies for the preparation and treatment of heavy metal mixed wastes, contaminated soils, and mixed mercury wastes are being considered at the Savannah River Site (SRS), a DOE nuclear material processing facility operated by Westinghouse Savannah River Company (WSRC). The proposed treatment technologies to be included at the Hazardous Waste/Mixed Waste Treatment Building at SRS are based on the regulatory requirements, projected waste volumes, existing technology, cost effectiveness, and project schedule. Waste sorting and size reduction are the initial step in the treatment process. After sorting/size reduction the wastes would go to the next applicable treatment module. For solid heavy metal mixed wastes the proposed treatment is macroencapsulation using a thermoplastic polymer. This process reduces the leachability of hazardous constituents from the waste and allows easy verification of the coating integrity. Stabilization and solidification in a cement matrix will treat a wide variety of wastes (i.e. soils, decontamination water). Some pretreatments may be required (i.e. Ph adjustment) before stabilization. Other pretreatments such as soil washing can reduce the amount of waste to be stabilized. Radioactive contaminated mercury waste at the SRS comes in numerous forms (i.e. process equipment, soils, and lab waste) with the required treatment of high mercury wastes being roasting/retorting and recovery. Any unrecyclable radioactive contaminated elemental mercury would be amalgamated, utilizing a batch system, before disposal.

  19. 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.

    1986-09-01

    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.

  20. 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.

  1. Integration of US Department of Energy contractor installations for the purpose of optimizing treatment, storage, and disposal of low-level radioactive waste (LLW)

    SciTech Connect (OSTI)

    Lucas, M.; Gnoose, J.; Coony, M.; Martin, E.; Piscitella, R.

    1998-02-01

    The US Department of Energy (DOE) manages a multibillion dollar environmental management (EM) program. In June 1996, the Assistant Secretary of Energy for EM issued a memorandum with guidance and a vision for a ten year planning process for the EM Program. The purpose of this process, which became known as the Accelerated Cleanup: Focus on 2006, is to make step changes within the DOE complex regarding the approach for making meaningful environmental cleanup progress. To augment the process, Assistant Secretary requested the site contractors to engage in an effort to identify and evaluate integration alternatives for EM waste stream treatment, storage, and disposal (TSD) that would parallel the 2006 Plan. In October 1996, ten DOE contractor installations began the task of identifying alternative opportunities for low level radioactive waste (LLW). Cost effective, efficient solutions were necessary to meet all requirements associated with storing, characterizing, treating, packaging, transporting, and disposing of LLW while protecting the workers` health and safety, and minimizing impacts to the environment. To develop these solutions, a systems engineering approach was used to establish the baseline requirements, to develop alternatives, and to evaluate the alternatives. Key assumptions were that unique disposal capabilities exist within the DOE that must be maintained; private sector disposal capability for some LLW may not continue to exist into the foreseeable future; and decisions made by the LLW Team must be made on a system or complex wide basis to fully realize the potential cost and schedule benefits. This integration effort promoted more accurate waste volume estimates and forecasts; enhanced recognition of existing treatment, storage, and disposal capabilities and capacities; and improved identification of cost savings across the complex.

  2. SYNERGIA Forum Integrated Municipal Solid Waste Management

    E-Print Network [OSTI]

    Columbia University

    2nd SYNERGIA Forum «Integrated Municipal Solid Waste Management: Recycling and Energy Change and Solid Waste Management" Anthony Mavropoulos President, Scientific Technical Committee, Chairman, SYNERGIA "Where Greece stands on the Ladder of Sustainable Waste Management " *Nikolaos

  3. Closed Fuel Cycle Waste Treatment Strategy

    SciTech Connect (OSTI)

    Vienna, J. D.; Collins, E. D.; Crum, J. V.; Ebert, W. L.; Frank, S. M.; Garn, T. G.; Gombert, D.; Jones, R.; Jubin, R. T.; Maio, V. C.; Marra, J. C.; Matyas, J.; Nenoff, T. M.; Riley, B. J.; Sevigny, G. J.; Soelberg, N. R.; Strachan, D. M.; Thallapally, P. K.; Westsik, J. H.

    2015-02-01

    This study is aimed at evaluating the existing waste management approaches for nuclear fuel cycle facilities in comparison to the objectives of implementing an advanced fuel cycle in the U.S. under current legal, regulatory, and logistical constructs. The study begins with the Global Nuclear Energy Partnership (GNEP) Integrated Waste Management Strategy (IWMS) (Gombert et al. 2008) as a general strategy and associated Waste Treatment Baseline Study (WTBS) (Gombert et al. 2007). The tenets of the IWMS are equally valid to the current waste management study. However, the flowsheet details have changed significantly from those considered under GNEP. In addition, significant additional waste management technology development has occurred since the GNEP waste management studies were performed. This study updates the information found in the WTBS, summarizes the results of more recent technology development efforts, and describes waste management approaches as they apply to a representative full recycle reprocessing flowsheet. Many of the waste management technologies discussed also apply to other potential flowsheets that involve reprocessing. These applications are occasionally discussed where the data are more readily available. The report summarizes the waste arising from aqueous reprocessing of a typical light-water reactor (LWR) fuel to separate actinides for use in fabricating metal sodium fast reactor (SFR) fuel and from electrochemical reprocessing of the metal SFR fuel to separate actinides for recycle back into the SFR in the form of metal fuel. The primary streams considered and the recommended waste forms include; Tritium in low-water cement in high integrity containers (HICs); Iodine-129: As a reference case, a glass composite material (GCM) formed by the encapsulation of the silver Mordenite (AgZ) getter material in a low-temperature glass is assumed. A number of alternatives with distinct advantages are also considered including a fused silica waste form with encapsulated nano-sized AgI crystals; Carbon-14 immobilized as a CaCO3 in a cement waste form; Krypton-85 stored as a compressed gas; An aqueous reprocessing high-level waste (HLW) raffinate waste immobilized by the vitrification process; An undissolved solids (UDS) fraction from aqueous reprocessing of LWR fuel either included in the borosilicate HLW glass or immobilized in the form of a metal alloy or titanate ceramics; Zirconium-based LWR fuel cladding hulls and stainless steel (SS) fuel assembly hardware super-compacted for disposal or purified for reuse (or disposal as low-level waste, LLW) of Zr by reactive gas separations; Electrochemical process salt HLW incorporated into a glass bonded Sodalite waste form; and Electrochemical process UDS and SS cladding hulls melted into an iron based alloy waste form. Mass and volume estimates for each of the recommended waste forms based on the source terms from a representative flowsheet are reported. In addition to the above listed primary waste streams, a range of secondary process wastes are generated by aqueous reprocessing of LWR fuel, metal SFR fuel fabrication, and electrochemical reprocessing of SFR fuel. These secondary wastes have been summarized and volumes estimated by type and classification. The important waste management data gaps and research needs have been summarized for each primary waste stream and selected waste process.

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

    Energy Savers [EERE]

    - October 2013 October 2013 Observation of Waste Treatment and Immobilization Plant Low Activity Waste Melter and Melter Off-gas Process System Hazards Analysis Activities...

  5. 8-Waste treatment and disposal A. Responsibility for waste management

    E-Print Network [OSTI]

    8- Waste treatment and disposal A. Responsibility for waste management 1. Each worker is responsible for correctly bagging and labeling his/her own waste. 2. A BSL3 technician will be responsible for transporting and autoclaving the waste. Waste will be autoclaved once or twice per day, depending on use

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

    SciTech Connect (OSTI)

    CRAWFORD TW

    2008-07-17

    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.

  7. Waste Form Degradation Model Integration for Engineered Materials...

    Office of Environmental Management (EM)

    Waste Form Degradation Model Integration for Engineered Materials Performance Waste Form Degradation Model Integration for Engineered Materials Performance The collaborative...

  8. Bioelectrochemical Integration of Waste Heat Recovery, Waste...

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

    oxygen demand (COD) and availability of low-grade waste heat sources. The pulp and paper industry and other industries are also potential MHRC users. Project Description This...

  9. Bioelectrochemical Integration of Waste Heat Recovery, Waste...

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

    - Allentown, PA A microbial reverse electrodialysis technology will be combined with waste heat recovery to convert effluents into electricity and chemical products, including...

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

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

    June 2013 Hanford Waste Treatment and Immobilization Plant Low Activity Waste Melter Off-gas Process System Hazards Analysis Activity Observation HIAR-WTP-2013-05-13 This...

  11. Mixed waste characterization, treatment & disposal focus area

    SciTech Connect (OSTI)

    NONE

    1996-08-01

    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.

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

    SciTech Connect (OSTI)

    Ramsey, William Gene

    2013-08-15

    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.

  13. Global Nuclear Energy Partnership Waste Treatment Baseline

    SciTech Connect (OSTI)

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

    2008-05-01

    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.

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

    Office of Environmental Management (EM)

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

  15. Waste Treatment and Immobilation Plant Pretreatment Facility

    Office of Environmental Management (EM)

    7 Technology Readiness Assessment for the Waste Treatment and Immobilization Plant (WTP) Pretreatment Facility L. Holton D. Alexander M. Johnson H. Sutter August 2007 Prepared by...

  16. 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...

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

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

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

  18. Buried Waste Integrated Demonstration Plan

    SciTech Connect (OSTI)

    Kostelnik, K.M.

    1991-12-01

    This document presents the plan of activities for the Buried Waste Integrated Demonstration (BWID) program which supports the environmental restoration (ER) objectives of the Department of Energy (DOE) Complex. Discussed in this plan are the objectives, organization, roles and responsibilities, and the process for implementing and managing BWID. BWID is hosted at the Idaho National Engineering Laboratory (INEL), but involves participants from throughout the DOE Complex, private industry, universities, and the international community. These participants will support, demonstrate, and evaluate a suite of advanced technologies representing a comprehensive remediation system for the effective and efficient remediation of buried waste. The processes for identifying technological needs, screening candidate technologies for applicability and maturity, selecting appropriate technologies for demonstration, field demonstrating, evaluation of results and transferring technologies to environmental restoration programs are also presented. This document further describes the elements of project planning and control that apply to BWID. It addresses the management processes, operating procedures, programmatic and technical objectives, and schedules. Key functions in support of each demonstration such as regulatory coordination, safety analyses, risk evaluations, facility requirements, and data management are presented.

  19. Radioactive waste treatment technologies and environment

    SciTech Connect (OSTI)

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

    2007-07-01

    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)

  20. 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.

    2013-08-29

    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

  1. 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

  2. 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...

  3. Hanford Tank Waste Retrieval, Treatment, and Disposition Framework...

    Office of Environmental Management (EM)

    Hanford Tank Waste Retrieval, Treatment, and Disposition Framework Hanford Tank Waste Retrieval, Treatment, and Disposition Framework Forty years of plutonium production at the...

  4. 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...

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

    Office of Environmental Management (EM)

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

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

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

    Waste Treatment and Immobilization Plant - June 2014 June 2014 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality This report documents the...

  7. Enterprise Assessments Review of the Hanford Site Waste Treatment...

    Energy Savers [EERE]

    Site Waste Treatment and Immobilization Plant Construction Quality - June 2015 Enterprise Assessments Review of the Hanford Site Waste Treatment and Immobilization Plant...

  8. Radioactive Liquid Waste Treatment Facility: Environmental Information Document

    SciTech Connect (OSTI)

    Haagenstad, H.T.; Gonzales, G.; Suazo, I.L. [Los Alamos National Lab., NM (United States)

    1993-11-01

    At Los Alamos National Laboratory (LANL), the treatment of radioactive liquid waste is an integral function of the LANL mission: to assure U.S. military deterrence capability through nuclear weapons technology. As part of this mission, LANL conducts nuclear materials research and development (R&D) activities. These activities generate radioactive liquid waste that must be handled in a manner to ensure protection of workers, the public, and the environment. Radioactive liquid waste currently generated at LANL is treated at the Radioactive Liquid Waste Treatment Facility (RLWTF), located at Technical Area (TA)-50. The RLWTF is 30 years old and nearing the end of its useful design life. The facility was designed at a time when environmental requirements, as well as more effective treatment technologies, were not inherent in engineering design criteria. The evolution of engineering design criteria has resulted in the older technology becoming less effective in treating radioactive liquid wastestreams in accordance with current National Pollutant Discharge Elimination System (NPDES) and Department of Energy (DOE) regulatory requirements. Therefore, to support ongoing R&D programs pertinent to its mission, LANL is in need of capabilities to efficiently treat radioactive liquid waste onsite or to transport the waste off site for treatment and/or disposal. The purpose of the EID is to provide the technical baseline information for subsequent preparation of an Environmental Impact Statement (EIS) for the RLWTF. This EID addresses the proposed action and alternatives for meeting the purpose and need for agency action.

  9. 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)

    2010-06-15

    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.

  10. Waste water treatment cuts plant's pollution

    SciTech Connect (OSTI)

    Not Available

    1984-01-09

    New waste water treatment facilities at the U.S. Oil and Refining Co. refinery, Tacoma, Wash., have allowed that plant to exceed NPDES (National Pollution Discharge Elimination System) standards for effluent discharge. This comes in an area where maintaining water quality is a sensitive public issue. The waste treatment system at the 25,000 b/d refinery enables it to discharge negligible quantities of waterborne pollutants, according to Envirex Inc. Envirex designed and built the activated sludge waste treatment system at the refinery (Fig. 1). The system utilizes large rotating vertical discs for aeration of the waste water. These discs churn air into the waste water. They also keep the solidsladen water moving in an orbital path in a specially constructed treatment basin. The rotating discs and flowing water facilitate formation of large floc particles which are conducive to solids capture. A higher concentration of mixed-liquor suspended solids (MLSS) is therefore possible, enhancing the efficient removal of waste materials from the water.

  11. Buried waste integrated demonstration FY 94 deployment plan

    SciTech Connect (OSTI)

    Hyde, R.A.; Walker, S.; Garcia, M.M.

    1994-05-01

    The Buried Waste Integrated Demonstration (BWID) is a program funded by the U.S. Department of Energy Office of Technology Development. BWID supports the applied research, development, demonstration, testing, and evaluation of a suite of advanced technologies that together form a comprehensive remediation system for the effective and efficient remediation of buried waste. The fiscal year (FY) 1994 effort will fund thirty-eight technologies in five areas of buried waste site remediation: site characterization, waste characterization, retrieval, treatment, and containment/stabilization. This document is the basic operational planning document for deployment of all BWID projects. Discussed in this document are the BWID preparations for INEL field demonstrations, INEL laboratory demonstrations, non-INEL demonstrations, and paper studies. Each technology performing tests will prepare a test plan to detail the specific procedures, objectives, and tasks of each test. Therefore, information specific to testing each technology is intentionally omitted from this document.

  12. Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford...

    Office of Environmental Management (EM)

    More Documents & Publications Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility EMAB Reports and Recommendations - September 2010 System Planning for...

  13. Enterprise Assessments Review of the Hanford Site Waste Treatment...

    Office of Environmental Management (EM)

    Hazards Analysis Report for the Low-Activity Waste Facility Reagent Systems - July 2015 Enterprise Assessments Review of the Hanford Site Waste Treatment and Immobilization Plant...

  14. Enterprise Assessments Review of the Hanford Site Waste Treatment...

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

    Review of the Hanford Site Waste Treatment and Immobilization Plant Low-Activity Waste Facility Hazards Analysis Reports for the Melter and Melter Offgas Systems - September 2015...

  15. Waste Treatment and Immobilization Plant (WTP) Analytical Laboratory...

    Office of Environmental Management (EM)

    2 Technology Readiness Assessment for the Waste Treatment and Immobilization Plant (WTP) Analytical Laboratory, Balance of Facilities and LAW Waste Vitrification Facilities L....

  16. Enterprise Assessments Review of the Hanford Site Waste Treatment...

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

    Enterprise Assessments Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality - June 2015 Enterprise Assessments Review of the Hanford Site Waste...

  17. Medical waste treatment and decontamination system

    DOE Patents [OSTI]

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

    2001-01-01

    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.

  18. 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

  19. Zinc Bromide Waste Solution Treatment Options

    SciTech Connect (OSTI)

    Langston, C.A.

    2001-01-16

    The objective of this effort was to identify treatment options for 20,000 gallons of low-level radioactively contaminated zinc bromide solution currently stored in C-Area. These options will be relevant when the solutions are declared waste.

  20. Waste Treatment Plant Liquid Effluent Treatability Evaluation

    SciTech Connect (OSTI)

    LUECK, K.J.

    2001-06-07

    Bechtel National, Inc. (BNI) provided a forecast of the radioactive, dangerous liquid effluents expected to be generated by the Waste Treatment Plant (WTP). The forecast represents the liquid effluents generated from the processing of 25 distinct batches of tank waste through the WTP. The WTP liquid effluents will be stored, treated, and disposed of in the Liquid Effluent Retention Facility (LERF) and the Effluent Treatment Facility (ETF). Fluor Hanford, Inc. (FH) evaluated the treatability of the WTP liquid effluents in the LERFIETF. The evaluation was conducted by comparing the forecast to the LERFIETF treatability envelope, which provides information on the items that determine if a liquid effluent is acceptable for receipt and treatment at the LERFIETF. The WTP liquid effluent forecast is outside the current LERFlETF treatability envelope. There are several concerns that must be addressed before the WTP liquid effluents can be accepted at the LERFIETF.

  1. Handbook of industrial and hazardous wastes treatment. 2nd ed.

    SciTech Connect (OSTI)

    Lawrence Wang; Yung-Tse Hung; Howard Lo; Constantine Yapijakis

    2004-06-15

    This expanded Second Edition offers 32 chapters of industry- and waste-specific analyses and treatment methods for industrial and hazardous waste materials - from explosive wastes to landfill leachate to wastes produced by the pharmaceutical and food industries. Key additional chapters cover means of monitoring waste on site, pollution prevention, and site remediation. Including a timely evaluation of the role of biotechnology in contemporary industrial waste management, the Handbook reveals sound approaches and sophisticated technologies for treating: textile, rubber, and timber wastes; dairy, meat, and seafood industry wastes; bakery and soft drink wastes; palm and olive oil wastes; pesticide and livestock wastes; pulp and paper wastes; phosphate wastes; detergent wastes; photographic wastes; refinery and metal plating wastes; and power industry wastes. This final chapter, entitled 'Treatment of power industry wastes' by Lawrence K. Wang, analyses the stream electric power generation industry, where combustion of fossil fuels coal, oil, gas, supplies heat to produce stream, used then to generate mechanical energy in turbines, subsequently converted to electricity. Wastes include waste waters from cooling water systems, ash handling systems, wet-scrubber air pollution control systems, and boiler blowdown. Wastewaters are characterized and waste treatment by physical and chemical systems to remove pollutants is presented. Plant-specific examples are provided.

  2. Process modeling for the Integrated Thermal Treatment System (ITTS) study

    SciTech Connect (OSTI)

    Liebelt, K.H.; Brown, B.W.; Quapp, W.J.

    1995-09-01

    This report describes the process modeling done in support of the integrated thermal treatment system (ITTS) study, Phases 1 and 2. ITTS consists of an integrated systems engineering approach for uniform comparison of widely varying thermal treatment technologies proposed for treatment of the contact-handled mixed low-level wastes (MLLW) currently stored in the U.S. Department of Energy complex. In the overall study, 19 systems were evaluated. Preconceptual designs were developed that included all of the various subsystems necessary for a complete installation, from waste receiving through to primary and secondary stabilization and disposal of the processed wastes. Each system included the necessary auxiliary treatment subsystems so that all of the waste categories in the complex were fully processed. The objective of the modeling task was to perform mass and energy balances of the major material components in each system. Modeling of trace materials, such as pollutants and radioactive isotopes, were beyond the present scope. The modeling of the main and secondary thermal treatment, air pollution control, and metal melting subsystems was done using the ASPEN PLUS process simulation code, Version 9.1-3. These results were combined with calculations for the remainder of the subsystems to achieve the final results, which included offgas volumes, and mass and volume waste reduction ratios.

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

    Office of Environmental Management (EM)

    More Documents & Publications Voluntary Protection Program Onsite Review, Intermech Inc., Waste Treatment Plant Construction Site - November 2013 Voluntary Protection Program...

  4. Commercial waste treatment program annual progress report for FY 1983

    SciTech Connect (OSTI)

    McElroy, J.L.; Burkholder, H.C. (comps.)

    1984-02-01

    This annual report describes progress during FY 1983 relating to technologies under development by the Commercial Waste Treatment Program, including: development of glass waste form and vitrification equipment for high-level wastes (HLW); waste form development and process selection for transuranic (TRU) wastes; pilot-scale operation of a radioactive liquid-fed ceramic melter (LFCM) system for verifying the reliability of the reference HLW treatment proces technology; evaluation of treatment requirements for spent fuel as a waste form; second-generation waste form development for HLW; and vitrification process control and product quality assurance technologies.

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

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

    Treatment and Immobilization Plant - March 2014 March 2014 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality This report documents the...

  6. Aqueous Waste Treatment Plant at Aldermaston

    SciTech Connect (OSTI)

    Keene, D. [RWE NUKEM, Ltd, 424 Harwell, Didcot, Oxfordshire, OX 110GJ (United Kingdom); Fowler, J.; Frier, S. [AWE plc, Aldermaston, Berkshire RG7 4PR (United Kingdom)

    2006-07-01

    For over half a century the Pangbourne Pipeline formed part of AWE's liquid waste management system. Since 1952 the 11.5 mile pipeline carried pre-treated wastewater from the Aldermaston site for safe dispersal in the River Thames. Such discharges were in strict compliance with the exacting conditions demanded by all regulatory authorities, latterly, those of the Environment Agency. In March 2005 AWE plc closed the Pangbourne Pipeline and ceased discharges of treated active aqueous waste to the River Thames via this route. The ability to effectively eliminate active liquid discharges to the environment is thanks to an extensive programme of waste minimization on the Aldermaston site, together with the construction of a new Waste Treatment Plant (WTP). Waste minimization measures have reduced the effluent arisings by over 70% in less than four years. The new WTP has been built using best available technology (evaporation followed by reverse osmosis) to remove trace levels of radioactivity from wastewater to exceptionally stringent standards. Active operation has confirmed early pilot scale trials, with the plant meeting throughput and decontamination performance targets, and final discharges being at or below limits of detection. The performance of the plant allows the treated waste to be discharged safely as normal industrial effluent from the AWE site. Although the project has had a challenging schedule, the project was completed on programme, to budget and with an exemplary safety record (over 280,000 hours in construction with no lost time events) largely due to a pro-active partnering approach between AWE plc and RWE NUKEM and its sub-contractors. (authors)

  7. Integrated solid waste management of Sevierville, Tennessee

    SciTech Connect (OSTI)

    1995-11-01

    The subject document reports the results of an in-depth investigation of the fiscal year 1992 cost of the City of Sevierville, Tennessee integrated municipal solid waste management (IMSWM) system, the energy consumed to operate the system, and the environmental performance requirements for each of the system`s waste-processing and disposal facilities. Actual data from records kept by participants is reported in this document. Every effort was made to minimize the use of assumptions, and no attempt is made to interpret the data reported. Analytical approaches are documented so that interested analysts may perform manipulation or further analysis of the data. As such, the report is a reference document for MSW management professionals who are interested in the actual costs and energy consumption for a one-year period, of an operating IMSWM systems.

  8. Integrated solid waste management of Scottsdale, Arizona

    SciTech Connect (OSTI)

    1995-11-01

    The subject document reports the results of an in-depth investigation of the fiscal year 1992 cost of the city of Scottsdale, Arizona, integrated municipal solid waste management (IMSWM) system, the energy consumed to operate the system, and the environmental performance requirements for each of the system`s waste-processing and disposal facilities. The document reports actual data from records kept by participants. Every effort was made to minimize the use of assumptions, and no attempt is made to interpret the data reported. Analytical approaches are documented so that interested analysts may per-form manipulation or further analysis of the data. As such, the report is a reference document for municipal solid waste (MSW) management professionals who are interested in the actual costs and energy consumption, for a 1-year period, of an operating IMSWM system. The report is organized into two main parts. The first part is the executive summary and case study portion of the report. The executive summary provides a basic description of the study area and selected economic and energy information. Within the case study are detailed descriptions of each component operating during the study period; the quantities of solid waste collected, processed, and marketed within the study boundaries; the cost of MSW in Scottsdale; an energy usage analysis; a review of federal, state, and local environmental requirement compliance; a reference section; and a glossary of terms. The second part of the report focuses on a more detailed discourse on the above topics. In addition, the methodology used to determine the economic costs and energy consumption of the system components is found in the second portion of this report. The methodology created for this project will be helpful for those professionals who wish to break out the costs of their own integrated systems.

  9. Wireless handheld scanners integrated with waste tracking

    SciTech Connect (OSTI)

    R. S. Anderson

    2000-07-23

    The US Department of Energy (DOE) Idaho National Engineering and Environmental Laboratory (INEEL) has embraced mobile wireless technology to help the disposition of hazardous and mixed radiological waste. The following paper describes one application the INEEL developed to increase the data accuracy and near-real time reporting requirements for waste management. With the continuous operational demands at the ''site'', it was difficult to sustain an accurate, up-to-date database required for regulatory compliance audits and reporting. Incorporating wireless mobile technology, the INEEL was able to increase the accuracy while reducing the data delay times previously encountered. Installation issues prolonged the project along with obstacles encountered with operations personnel. However, the success of this project was found in persistence and management support as well as the technology itself. Future wireless, mobile computing will continue at the INEEL for years to come based on a successful project that was able to integrate new technology to an existing waste management system with proven, increased data accuracy.

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

    SciTech Connect (OSTI)

    Not Available

    1992-04-01

    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.

  11. Waste treatment at the La Hague and Marcoule sites

    SciTech Connect (OSTI)

    NONE

    1995-04-01

    In this report, an overview of waste treatment and solidification facilities located at the La Hague and Marcoule sites, which are owned and/or operated by Cogema, provided. The La Hague facilities described in this report include the following: The STE3 liquid effluent treatment facility (in operation); the AD2 solid waste processing facility (also in operation); and the UCD alpha waste treatment facility (under construction). The Marcoule facilities described in this report, both of which are in operation, include the following: The STEL-EVA liquid effluent treatment facilities for the entire site; and the alpha waste incinerator of the UPI plant. This report is organized into four sections: this introduction, low-level waste treatment at La Hague, low-level waste treatment at Marcoule, and new process development. including the solvent pyrolysis process currently in the development stage for Cogema`s plants.

  12. Enterprise Assessments Review of the Hanford Site Waste Treatment...

    Office of Environmental Management (EM)

    Office of Enterprise Assessments Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality June 2015 Office of Nuclear Safety and Environmental...

  13. Review of the Hanford Site Waste Treatment and Immobilization...

    Office of Environmental Management (EM)

    Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality May 2011 August 2012 Office of Safety and Emergency Management Evaluations Office of...

  14. Review of the Hanford Site Waste Treatment and Immobilization...

    Office of Environmental Management (EM)

    Independent Oversight Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality May 2011 October 2012 Office of Safety and Emergency Management...

  15. Enterprise Assessments Review of the Hanford Site Waste Treatment...

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

    Project Engineering Processes - October 2015 Enterprise Assessments Review of the Hanford Site Waste Treatment and Immobilization Plant Project Engineering Processes - October 2015...

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

    Open Energy Info (EERE)

    Apps Datasets Community Login | Sign Up Search Page Edit with form History ORS 466 - Storage, Treatment, and Disposal of Hazardous Waste and Materials Jump to: navigation, search...

  17. 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...

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

    Office of Environmental Management (EM)

    and Immobilization Plant - December 2013 December 2013 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality This report documents the...

  19. Voluntary Protection Program Onsite Review, Waste Treatment Project...

    Office of Environmental Management (EM)

    Hanford Site - June 2010 Voluntary Protection Program Onsite Review, Intermech Inc., Waste Treatment Plant Construction Site - November 2013 Voluntary Protection Program...

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

    Energy Savers [EERE]

    and Immobilization Plant - January 2015 January, 2015 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U.S. Department of...

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

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

    and Immobilization Plant - September 2014 September 2014 Review of the Hanford Site Waste Treatment and Immobilization Plant Construction Quality The U.S. Department of...

  2. Buried Waste Integrated Demonstration Plan. Revision 1

    SciTech Connect (OSTI)

    Kostelnik, K.M.

    1991-12-01

    This document presents the plan of activities for the Buried Waste Integrated Demonstration (BWID) program which supports the environmental restoration (ER) objectives of the Department of Energy (DOE) Complex. Discussed in this plan are the objectives, organization, roles and responsibilities, and the process for implementing and managing BWID. BWID is hosted at the Idaho National Engineering Laboratory (INEL), but involves participants from throughout the DOE Complex, private industry, universities, and the international community. These participants will support, demonstrate, and evaluate a suite of advanced technologies representing a comprehensive remediation system for the effective and efficient remediation of buried waste. The processes for identifying technological needs, screening candidate technologies for applicability and maturity, selecting appropriate technologies for demonstration, field demonstrating, evaluation of results and transferring technologies to environmental restoration programs are also presented. This document further describes the elements of project planning and control that apply to BWID. It addresses the management processes, operating procedures, programmatic and technical objectives, and schedules. Key functions in support of each demonstration such as regulatory coordination, safety analyses, risk evaluations, facility requirements, and data management are presented.

  3. Sodium-Bearing Waste Treatment Alternatives Implementation Study

    SciTech Connect (OSTI)

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

    2004-07-01

    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).

  4. 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)

    1997-01-01

    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.

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

    DOE Patents [OSTI]

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

    1997-03-18

    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.

  6. 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.

    2011-02-24

    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.

  7. 2020 Vision for Tank Waste Cleanup (One System Integration) - 12506

    SciTech Connect (OSTI)

    Harp, Benton; Charboneau, Stacy; Olds, Erik [US DOE (United States)

    2012-07-01

    The mission of the Department of Energy's Office of River Protection (ORP) is to safely retrieve and treat the 56 million gallons of Hanford's tank waste and close the Tank Farms to protect the Columbia River. The millions of gallons of waste are a by-product of decades of plutonium production. After irradiated fuel rods were taken from the nuclear reactors to the processing facilities at Hanford they were exposed to a series of chemicals designed to dissolve away the rod, which enabled workers to retrieve the plutonium. Once those chemicals were exposed to the fuel rods they became radioactive and extremely hot. They also couldn't be used in this process more than once. Because the chemicals are caustic and extremely hazardous to humans and the environment, underground storage tanks were built to hold these chemicals until a more permanent solution could be found. The Cleanup of Hanford's 56 million gallons of radioactive and chemical waste stored in 177 large underground tanks represents the Department's largest and most complex environmental remediation project. Sixty percent by volume of the nation's high-level radioactive waste is stored in the underground tanks grouped into 18 'tank farms' on Hanford's central plateau. Hanford's mission to safely remove, treat and dispose of this waste includes the construction of a first-of-its-kind Waste Treatment Plant (WTP), ongoing retrieval of waste from single-shell tanks, and building or upgrading the waste feed delivery infrastructure that will deliver the waste to and support operations of the WTP beginning in 2019. Our discussion of the 2020 Vision for Hanford tank waste cleanup will address the significant progress made to date and ongoing activities to manage the operations of the tank farms and WTP as a single system capable of retrieving, delivering, treating and disposing Hanford's tank waste. The initiation of hot operations and subsequent full operations of the WTP are not only dependent upon the successful design and construction of the WTP, but also on appropriately preparing the tank farms and waste feed delivery infrastructure to reliably and consistently deliver waste feed to the WTP for many decades. The key components of the 2020 vision are: all WTP facilities are commissioned, turned-over and operational, achieving the earliest possible hot operations of completed WTP facilities, and supplying low-activity waste (LAW) feed directly to the LAW Facility using in-tank/near tank supplemental treatment technologies. A One System Integrated Project Team (IPT) was recently formed to focus on developing and executing the programs that will be critical to successful waste feed delivery and WTP startup. The team is comprised of members from Bechtel National, Inc. (BNI), Washington River Protection Solutions LLC (WRPS), and DOE-ORP and DOE-WTP. The IPT will combine WTP and WRPS capabilities in a mission-focused model that is clearly defined, empowered and cost efficient. The genesis for this new team and much of the 2020 vision is based on the work of an earlier team that was tasked with identifying the optimum approach to startup, commissioning, and turnover of WTP facilities for operations. This team worked backwards from 2020 - a date when the project will be completed and steady-state operations will be underway - and identified success criteria to achieving safe and efficient operations of the WTP. The team was not constrained by any existing contract work scope, labor, or funding parameters. Several essential strategies were identified to effectively realize the one-system model of integrated feed stream delivery, WTP operations, and product delivery, and to accomplish the team's vision of hot operations beginning in 2016: - Use a phased startup and turnover approach that will allow WTP facilities to be transitioned to an operational state on as short a timeline as credible. - Align Tank Farm (TF) and WTP objectives such that feed can be supplied to the WTP when it is required for hot operations. - Ensure immobilized waste and waste recycle streams can be recei

  8. FY 1996 solid waste integrated life-cycle forecast characteristics summary. Volumes 1 and 2

    SciTech Connect (OSTI)

    Templeton, K.J.

    1996-05-23

    For the past six years, a waste volume forecast has been collected annually from onsite and offsite generators that currently ship or are planning to ship solid waste to the Westinghouse Hanford Company`s Central Waste Complex (CWC). This document provides a description of the physical waste forms, hazardous waste constituents, and radionuclides of the waste expected to be shipped to the CWC from 1996 through the remaining life cycle of the Hanford Site (assumed to extend to 2070). In previous years, forecast data has been reported for a 30-year time period; however, the life-cycle approach was adopted this year to maintain consistency with FY 1996 Multi-Year Program Plans. This document is a companion report to two previous reports: the more detailed report on waste volumes, WHC-EP-0900, FY1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary and the report on expected containers, WHC-EP-0903, FY1996 Solid Waste Integrated Life-Cycle Forecast Container Summary. All three documents are based on data gathered during the FY 1995 data call and verified as of January, 1996. These documents are intended to be used in conjunction with other solid waste planning documents as references for short and long-term planning of the WHC Solid Waste Disposal Division`s treatment, storage, and disposal activities over the next several decades. This document focuses on two main characteristics: the physical waste forms and hazardous waste constituents of low-level mixed waste (LLMW) and transuranic waste (both non-mixed and mixed) (TRU(M)). The major generators for each waste category and waste characteristic are also discussed. The characteristics of low-level waste (LLW) are described in Appendix A. In addition, information on radionuclides present in the waste is provided in Appendix B. The FY 1996 forecast data indicate that about 100,900 cubic meters of LLMW and TRU(M) waste is expected to be received at the CWC over the remaining life cycle of the site. Based on ranges provided by the waste generators, this baseline volume could fluctuate between a minimum of about 59,720 cubic meters and a maximum of about 152,170 cubic meters. The range is primarily due to uncertainties associated with the Tank Waste Remediation System (TWRS) program, including uncertainties regarding retrieval of long-length equipment, scheduling, and tank retrieval technologies.

  9. Method for aqueous radioactive waste treatment

    DOE Patents [OSTI]

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

    1994-03-29

    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.

  10. Method for aqueous radioactive waste treatment

    DOE Patents [OSTI]

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

    1994-01-01

    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.

  11. Cold Spring Harbor Laboratory Waste Water Treatment Plant [The Inhabited Landscape: An Exhibition

    E-Print Network [OSTI]

    Architects, Centerbrook

    1988-01-01

    Spring Harbor Laboratory Waste Water Treatment Plant JuryThe Cold Spring Harbor Waste Water Treatment Plant makes aA Cold Spring Harbor Waste Water Treatment Plant Photograph

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

    SciTech Connect (OSTI)

    Jacobs, Torsten; Aign, Joerg

    2013-07-01

    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)

  13. Montana Integrated Waste Management Act (Montana)

    Broader source: Energy.gov [DOE]

    This legislation sets goals for the reduction of solid waste generated by households, businesses, and governments, through source reduction, reuse, recycling, and composting. The state aims to...

  14. Performance Enhancements to the Hanford Waste Treatment and Immobilization Plant Low-Activity Waste Vitrification System

    SciTech Connect (OSTI)

    Hamel, W. F. [Office of River Protection, U.S. Department of Energy, 2400 Stevens Drive, Richland, WA 99354 (United States); Gerdes, K. [U.S. Department of Energy, 19901 Germantown Road, Germantown, MD 20874 (United States); Holton, L. K. [Pacific Northwest National Laboratory, PO Box 999, Richland, WA 99352 (United States); Pegg, I.L. [Vitreous State Laboratory, The Catholic University of America, 620 Michigan Avenue NE, Washington, DC 20064 (United States); Bowan, B.W. [Duratek, Inc., 10100 Old Columbia Road, Columbia, Maryland 21046 (United States)

    2006-07-01

    The U.S Department of Energy Office of River Protection (DOE-ORP) is constructing a Waste Treatment and Immobilization Plant (WTP) for the treatment and vitrification of underground tank wastes stored at the Hanford Site in Washington State. The WTP comprises four major facilities: a pretreatment facility to separate the tank waste into high level waste (HLW) and low-activity waste (LAW) process streams, a HLW vitrification facility to immobilize the HLW fraction; a LAW vitrification facility to immobilize the LAW fraction, and an analytical laboratory to support the operations of all four treatment facilities. DOE has established strategic objectives to optimize the performance of the WTP facilities and the LAW and HLW waste forms to reduce the overall schedule and cost for treatment and vitrification of the Hanford tank wastes. This strategy has been implemented by establishing performance expectations in the WTP contract for the facilities and waste forms. In addition, DOE, as owner-operator of the WTP facilities, continues to evaluate 1) the design, to determine the potential for performance above the requirements specified in the WTP contract; and 2) improvements in production of the LAW and HLW waste forms. This paper reports recent progress directed at improving production of the LAW waste form. DOE's initial assessment, which is based on the work reported in this paper, is that the treatment rate of the WTP LAW vitrification facility can be increased by a factor of 2 to 4 with a combination of revised glass formulations, modest increases in melter glass operating temperatures, and a second-generation LAW melter with a larger surface area. Implementing these improvements in the LAW waste immobilization capability can benefit the LAW treatment mission by reducing the cost of waste treatment. (authors)

  15. B Plant low level waste system integrity assessment report

    SciTech Connect (OSTI)

    Walter, E.J.

    1995-09-01

    This document provides the report of the integrity assessment activities for the B Plant low level waste system. The assessment activities were in response to requirements of the Washington State Dangerous Waste Regulations, Washington Administrative Code (WAC), 173-303-640. This integrity assessment report supports compliance with Hanford Federal Facility Agreement and Consent Order interim milestone target action M-32-07-T03.

  16. SRNL report for the tank waste disposition integrated flowsheet: Corrosion testing

    SciTech Connect (OSTI)

    Wyrwas, R. B.

    2015-09-30

    A series of cyclic potentiodynamic polarization (CPP) tests were performed in support of the Tank Waste Disposition Integrated Flowsheet (TWDIF). The focus of the testing was to assess the effectiveness of the SRNL model for predicting the amount of nitrite inhibitor needed to prevent pitting induced by increasing halide concentrations. The testing conditions were selected to simulate the dilute process stream that is proposed to be returned to tank farms from treating the off-gas from the low activity waste melter in the Waste Treatment and Immobilization Plant.

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

    Energy Savers [EERE]

    and Immobilization Plant Low Activity Waste Facility Heating, Ventilation, and Air Conditioning Systems Hazards Analysis Activities HIAR-WTP-2014-01-27 This Independent...

  18. Development and demonstration of treatment technologies for the processing of US Department of Energy mixed waste

    SciTech Connect (OSTI)

    Berry, J.B.; Bloom, G.A. [Oak Ridge National Lab., TN (United States); Kuchynka, D.J. [Science Applications International Corp., Gaithersburg, MD (United States)

    1994-06-01

    Mixed waste is defined as waste contaminated with chemically hazardous (governed by the Resource Conservation and Recovery Act) and radioactive species [governed by US Department of Energy (DOE) orders]. The Mixed Waste Integrated Program (MWIP) is responding to the need for DOE mixed waste treatment technologies that meet these dual regulatory requirements. MWIP is developing emerging and innovative treatment technologies to determine process feasibility. Technology demonstrations will be used to determine whether processes are superior to existing technologies in reducing risk, minimizing life-cycle cost, and improving process performance. The Program also provides a forum for stakeholder and customer involvement in the technology development process. MWIP is composed of six technical areas that support a mixed-waste treatment system: (1) systems analysis, (2) materials handling, (3) chemical/physical separation, (4) waste destruction and stabilization, (5) off-gas treatment, and (6) final waste form stabilization. The status of the technical initiatives and the current research, development, and demonstration in each of these areas is described in this paper.

  19. 300 Area waste acid treatment system closure plan. Revision 1

    SciTech Connect (OSTI)

    NONE

    1996-03-01

    This section provides a description of the Hanford Site, identifies the proposed method of 300 Area Waste Acid Treatment System (WATS) closure, and briefly summarizes the contents of each chapter of this plan.

  20. SRS Tank 48H Waste Treatment Project Technology Readiness Assessment

    Office of Environmental Management (EM)

    Savannah River Site Tank 48H Waste Treatment Project Technology Readiness Assessment Harry D. Harmon Joan B. Berkowitz John C. DeVine, Jr. Herbert G. Sutter Joan K. Young...

  1. Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford...

    Office of Environmental Management (EM)

    NO. DE-AC27-01RV14136 - REPORT OF EXTERNAL FLOWSHEET REVIEW TEAM FOR THE HANFORD TANK WASTE TREATMENT AND IMMOBILIZATION PLANT - FINAL REPORT TITLED: "COMPREHENSIVE REVIEW OF THE...

  2. Treatability study of absorbent polymer waste form for mixed waste treatment

    SciTech Connect (OSTI)

    Herrmann, S. D.; Lehto, M. A.; Stewart, N. A.; Croft, A. D.; Kern, P. W.

    2000-02-10

    A treatability study was performed to develop and characterize an absorbent polymer waste form for application to low level (LLW) and mixed low level (MLLW) aqueous wastes at Argonne National Laboratory-West (ANL-W). In this study absorbent polymers proved effective at immobilizing aqueous liquid wastes in order to meet Land Disposal Restrictions for subsurface waste disposal. Treatment of aqueous waste with absorbent polymers provides an alternative to liquid waste solidification via high-shear mixing with clays and cements. Significant advantages of absorbent polymer use over clays and cements include ease of operations and waste volume minimization. Absorbent polymers do not require high-shear mixing as do clays and cements. Granulated absorbent polymer is poured into aqueous solutions and forms a gel which passes the paint filter test as a non-liquid. Pouring versus mixing of a solidification agent not only eliminates the need for a mixing station, but also lessens exposure to personnel and the potential for spread of contamination from treatment of radioactive wastes. Waste minimization is achieved as significantly less mass addition and volume increase is required of and results from absorbent polymer use than that of clays and cements. Operational ease and waste minimization translate into overall cost savings for LLW and MLLW treatment.

  3. Plasma-chemical waste treatment of acid gases

    SciTech Connect (OSTI)

    Harkness, J.B.L.; Doctor, R.D.; Daniels, E.J.

    1993-09-01

    The research to date has shown that a H{sub 2}S waste-treatment process based on plasma-chemical dissociation technology is compatible with refinery and high-carbon-oxide acid-gas streams. The minor amounts of impurities produced in the plasma-chemical reactor should be treatable by an internal catalytic reduction step. Furthermore, the plasma-chemical technology appears to be more efficient and more economical than the current technology. The principal key to achieving high conversions with relatively low energies of dissociation is the concept of the high-velocity, cyclonic-flow pattern in the plasma reaction zone coupled with the recycling of unconverted hydrogen sulfide. Future work will include testing the effects of components that might be carried over to the plasma reactor by ``upset`` conditions in the amine purification system of a plant and testing the plasma-chemical process on other industrial wastes streams that contain potentially valuable chemical reagents. The strategy for the commercialization of this technology is to form a Cooperative Research and Development Agreement with the Institute of Hydrogen Energy and Plasma Technology of the Russian Scientific Center/Kurchatov Institute and with an American start-up company to develop an ``American`` version of the process and to build a commercial-scale demonstration unit in the United States. The timetable proposed would involve building a ``field test`` facility which would test the plasma-chemical reactor and sulfur recovery unit operations on an industrial hydrogen sulfide waste s at a scale large enough to obtain the energy and material balance data required for a final analysis of the commercial potential of this technology. The field test would then be followed by construction of a commercial demonstration unit in two to three years. The commercial demonstration unit would be a fully integrated plant consisting of one commercial-scale module.

  4. DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced Mixed Waste Treatment Project: Contract will continue cleanup and waste operations at the Idaho Site

    Broader source: Energy.gov [DOE]

    Idaho Falls – In order to further meet the U.S. Department of Energy’s commitments to the citizens of the state of Idaho, the DOE today announced that it has selected Idaho Treatment Group, LLC (ITG) to perform waste processing at the Advanced Mixed Waste Treatment Project (AMWTP) at DOE’s Idaho Site near Idaho Falls.

  5. Integrating Total Quality Management (TQM) and hazardous waste management

    SciTech Connect (OSTI)

    Kirk, N.

    1993-11-01

    The Resource Conservation and Recovery Act (RCRA) of 1976 and its subsequent amendments have had a dramatic impact on hazardous waste management for business and industry. The complexity of this law and the penalties for noncompliance have made it one of the most challenging regulatory programs undertaken by the Environmental Protection Agency (EPA). The fundamentals of RCRA include ``cradle to grave`` management of hazardous waste, covering generators, transporters, and treatment, storage, and disposal facilities. The regulations also address extensive definitions and listing/identification mechanisms for hazardous waste along with a tracking system. Treatment is favored over disposal and emphasis is on ``front-end`` treatment such as waste minimization and pollution prevention. A study of large corporations such as Xerox, 3M, and Dow Chemical, as well as the public sector, has shown that well known and successful hazardous waste management programs emphasize pollution prevention and employment of techniques such as proactive environmental management, environmentally conscious manufacturing, and source reduction. Nearly all successful hazardous waste programs include some aspects of Total Quality Management, which begins with a strong commitment from top management. Hazardous waste management at the Rocky Flats Plant is further complicated by the dominance of ``mixed waste`` at the facility. The mixed waste stems from the original mission of the facility, which was production of nuclear weapons components for the Department of Energy (DOE). A Quality Assurance Program based on the criterion in DOE Order 5700.6C has been implemented at Rocky Flats. All of the elements of the Quality Assurance Program play a role in hazardous waste management. Perhaps one of the biggest waste management problems facing the Rocky Flats Plant is cleaning up contamination from a forty year mission which focused on production of nuclear weapon components.

  6. Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility |

    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 on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX E LIST OFAMERICA'S FUTURE. regulators consumerWaste Isolation

  7. Solid waste integrated cost analysis model: 1991 project year report

    SciTech Connect (OSTI)

    Not Available

    1991-01-01

    The purpose of the City of Houston's 1991 Solid Waste Integrated Cost Analysis Model (SWICAM) project was to continue the development of a computerized cost analysis model. This model is to provide solid waste managers with tool to evaluate the dollar cost of real or hypothetical solid waste management choices. Those choices have become complicated by the implementation of Subtitle D of the Resources Conservation and Recovery Act (RCRA) and the EPA's Integrated Approach to managing municipal solid waste;. that is, minimize generation, maximize recycling, reduce volume (incinerate), and then bury (landfill) only the remainder. Implementation of an integrated solid waste management system involving all or some of the options of recycling, waste to energy, composting, and landfilling is extremely complicated. Factors such as hauling distances, markets, and prices for recyclable, costs and benefits of transfer stations, and material recovery facilities must all be considered. A jurisdiction must determine the cost impacts of implementing a number of various possibilities for managing, handling, processing, and disposing of waste. SWICAM employs a single Lotus 123 spreadsheet to enable a jurisdiction to predict or assess the costs of its waste management system. It allows the user to select his own process flow for waste material and to manipulate the model to include as few or as many options as he or she chooses. The model will calculate the estimated cost for those choices selected. The user can then change the model to include or exclude waste stream components, until the mix of choices suits the user. Graphs can be produced as a visual communication aid in presenting the results of the cost analysis. SWICAM also allows future cost projections to be made.

  8. Treatment studies of paint stripping waste from plastic media blasting

    SciTech Connect (OSTI)

    Spence, R.D.

    1995-12-31

    Blasting with plastic media is used to strip paint and decontaminate surfaces. For disposal the plastic media is pulverized into a plastic dust. About 10 wt % of the waste from plastic media blasting is pulverized paint, which makes the waste a characteristically hazardous waste because of the presence of barium, cadmium, chromium and lead in the paint pigments. Four separate treatments of this hazardous waste were studied: (1) density separation to remove the paint, (2) self-encapsulation of the mix of plastic and paint dust into plastic pellets, (3) solidification/stabilization (S/S) into cementitious waste forms, and (4) low-temperature ashing to destroy the large mass of nonhazardous polymer. Two types of plast blasting wastes were studied: a urea formaldehyde thermoset polymer and an acrylic thermoplastic polymer (polymethylmethacrylate). Toxicity Characteristic Leach Procedure (TCLP) extraction concentrations for the treated and untreated wastes are listed. Density separation failed to adequately separate the paint with an aqueous carbonate solution. Self-encapsulation reduced the waste volume by about 50%, but did not meet TCLP criteria. Cementitious solidification gave the lowest TCLP concentrations, but increased the waste volume by about 50%. Low-temperature ashing at 600 C resulted in a mass decrease of 93 to 98% for the wastes; the metals remaining in the ash could be stabilized with cementitious solidification and still result in a volume decrease of 75 to 95 volume percent.

  9. 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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust,Field-effectWorking WithTelecentricN A 035(92/02)Management Waste Management OakWaste

  10. Glass Development for Treatment of LANL Evaporator Bottoms Waste

    SciTech Connect (OSTI)

    DE Smith; GF Piepel; GW Veazey; JD Vienna; ML Elliott; RK Nakaoka; RP Thimpke

    1998-11-20

    Vitrification is an attractive treatment option for meeting the stabilization and final disposal requirements of many plutonium (Pu) bearing materials and wastes at the Los Alamos National Laboratory (LANL) TA-55 facility, Rocky Flats Environmental Technology Site (RFETS), Hanford, and other Department of Energy (DOE) sites. The Environmental Protection Agency (EPA) has declared that vitrification is the "best demonstrated available technology" for high- level radioactive wastes (HLW) (Federal Register 1990) and has produced a handbook of vitriilcation technologies for treatment of hazardous and radioactive waste (US EPA, 1992). This technology has been demonstrated to convert Pu-containing materials (Kormanos, 1997) into durable (Lutze, 1988) and accountable (Forsberg, 1995) waste. forms with reduced need for safeguarding (McCulhun, 1996). The composition of the Evaporator Bottoms Waste (EVB) at LANL, like that of many other I%-bearing materials, varies widely and is generally unpredictable. The goal of this study is to optimize the composition of glass for EVB waste at LANL, and present the basic techniques and tools for developing optimized glass compositions for other Pu-bearing materials in the complex. This report outlines an approach for glass formulation with fixed property restrictions, using glass property-composition databases. This approach is applicable to waste glass formulation for many variable waste streams and vitrification technologies.. Also reported are the preliminary property data for simulated evaporator bottom glasses, including glass viscosity and glass leach resistance using the Toxicity Characteristic Leaching Procedure (TCLP).

  11. Logistics modeling of future solid waste storage, treatment, and disposal

    SciTech Connect (OSTI)

    Holter, G.M.; Stiles, D.L.; Shaver, S.R.; Armacost, L.L.

    1993-11-01

    Logistics modeling is a powerful analytical technique for effective planning of waste storage, treatment, and disposal activities. Logistics modeling facilitates analyses of alternate scenarios for future waste flows, facility schedules, and processing or handling capacities. These analyses provide an increased understanding of the specific needs for waste storage, treatment, and disposal while adequate time remains to plan accordingly. They also help to determine the sensitivity of these needs to various system parameters. This paper discusses a logistics modeling system developed by the Pacific Northwest Laboratory (PNL) to aid in solid waste planning for a large industrial complex managing many different types and classifications of waste. The basic needs for such a system are outlined, and the approach adopted in developing the system is described. A key component of this approach is the development of a conceptual model that provides a flexible framework for modeling the waste management system and addressing the range of logistics and economic issues involved. Developing an adequate description of the waste management system being analyzed is discussed. Examples are then provided of the types of analyses that have been conducted. The potential application of this modeling system to different settings is also examined.

  12. Waste Treatment Plant Project | Department of Energy

    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 on DeliciousMathematics And Statistics » USAJobs SearchAMERICA'S FUTURE. regulators02-03HeatWaste

  13. Mixed and Low-Level Waste Treatment Facility project

    SciTech Connect (OSTI)

    Not Available

    1992-04-01

    Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report, Appendix A, Environmental Regulatory Planning Documentation, identifies the regulatory requirements that would be imposed on the operation or construction of a facility designed to process the INEL's waste streams. These requirements are contained in five reports that discuss the following topics: (1) an environmental compliance plan and schedule, (2) National Environmental Policy Act requirements, (3) preliminary siting requirements, (4) regulatory justification for the project, and (5) health and safety criteria.

  14. Radioactive waste management treatments: A selection for the Italian scenario

    SciTech Connect (OSTI)

    Locatelli, G. [Univ. of Lincoln, Lincoln School of Engineering, Brayford Pool - Lincoln LN6 7TS (United Kingdom); Mancini, M. [Politecnico di Milano, Dept. of Management, Economics and Industrial Engineering, Via Lambruschini 4/B, Milano (Italy); Sardini, M. [Politecnico di Milano, Dept. of Energy, Via Lambruschini 4, Milano (Italy)

    2012-07-01

    The increased attention for radioactive waste management is one of the most peculiar aspects of the nuclear sector considering both reactors and not power sources. The aim of this paper is to present the state-of-art of treatments for radioactive waste management all over the world in order to derive guidelines for the radioactive waste management in the Italian scenario. Starting with an overview on the international situation, it analyses the different sources, amounts, treatments, social and economic impacts looking at countries with different industrial backgrounds, energetic policies, geography and population. It lists all these treatments and selects the most reasonable according to technical, economic and social criteria. In particular, a double scenario is discussed (to be considered in case of few quantities of nuclear waste): the use of regional, centralized, off site processing facilities, which accept waste from many nuclear plants, and the use of mobile systems, which can be transported among multiple nuclear sites for processing campaigns. At the end the treatments suitable for the Italian scenario are presented providing simplified work-flows and guidelines. (authors)

  15. 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...

  16. Eco-efficient waste glass recycling: Integrated waste management and green product development through LCA

    SciTech Connect (OSTI)

    Blengini, Gian Andrea, E-mail: blengini@polito.it [DISPEA - Department of Production Systems and Business Economics, Politecnico di Torino, Corso Duca degli Abruzzi 24, 10129 Turin (Italy); CNR-IGAG, Institute of Environmental Geology and Geo-Engineering, Corso Duca degli Abruzzi 24, 10129 Turin (Italy); Busto, Mirko, E-mail: mirko.busto@polito.it [DISPEA - Department of Production Systems and Business Economics, Politecnico di Torino, Corso Duca degli Abruzzi 24, 10129 Turin (Italy); Fantoni, Moris, E-mail: moris.fantoni@polito.it [DITAG - Department of Land, Environment and Geo-Engineering, Politecnico di Torino, Corso Duca degli Abruzzi 24, 10129 Turin (Italy); Fino, Debora, E-mail: debora.fino@polito.it [DISMIC - Department of Materials Science and Chemical Engineering, Politecnico di Torino, Corso Duca degli Abruzzi 24, 10129 Turin (Italy)

    2012-05-15

    Highlights: Black-Right-Pointing-Pointer A new eco-efficient recycling route for post-consumer waste glass was implemented. Black-Right-Pointing-Pointer Integrated waste management and industrial production are crucial to green products. Black-Right-Pointing-Pointer Most of the waste glass rejects are sent back to the glass industry. Black-Right-Pointing-Pointer Recovered co-products give more environmental gains than does avoided landfill. Black-Right-Pointing-Pointer Energy intensive recycling must be limited to waste that cannot be closed-loop recycled. - Abstract: As part of the EU Life + NOVEDI project, a new eco-efficient recycling route has been implemented to maximise resources and energy recovery from post-consumer waste glass, through integrated waste management and industrial production. Life cycle assessment (LCA) has been used to identify engineering solutions to sustainability during the development of green building products. The new process and the related LCA are framed within a meaningful case of industrial symbiosis, where multiple waste streams are utilised in a multi-output industrial process. The input is a mix of rejected waste glass from conventional container glass recycling and waste special glass such as monitor glass, bulbs and glass fibres. The green building product is a recycled foam glass (RFG) to be used in high efficiency thermally insulating and lightweight concrete. The environmental gains have been contrasted against induced impacts and improvements have been proposed. Recovered co-products, such as glass fragments/powders, plastics and metals, correspond to environmental gains that are higher than those related to landfill avoidance, whereas the latter is cancelled due to increased transportation distances. In accordance to an eco-efficiency principle, it has been highlighted that recourse to highly energy intensive recycling should be limited to waste that cannot be closed-loop recycled.

  17. Sodium-Bearing Waste Treatment, Applied Technology Plan

    SciTech Connect (OSTI)

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

    2003-06-01

    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.

  18. Waste form development for use with ORNL waste treatment facility sludge

    SciTech Connect (OSTI)

    Abotsi, G.M.K.; Bostick, W.D.

    1996-05-01

    A sludge that simulates Water Softening Sludge number 5 (WSS number 5 filtercake) at Oak Ridge National Laboratory was prepared and evaluated for its thermal behavior, volume reduction, stabilization, surface area and compressive strength properties. Compaction of the surrogate waste and the calcium oxide (produced by calcination) in the presence of paraffin resulted in cylindrical molds with various degrees of stability. This work has demonstrated that surrogate WSS number 5 at ORNL can be successfully stabilized by blending it with about 35 percent paraffin and compacting the mixture at 8000 psi. This compressive strength of the waste form is sufficient for temporary storage of the waste while long-term storage waste forms are developed. Considering the remarkable similarity between the surrogate and the actual filtercake, the findings of this project should be useful for treating the sludge generated by the waste treatment facility at ORNL.

  19. Mixed and low-level waste treatment facility project

    SciTech Connect (OSTI)

    Not Available

    1992-04-01

    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.

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

    SciTech Connect (OSTI)

    Brown, D.F.

    1994-10-17

    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.

  1. Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC).

    SciTech Connect (OSTI)

    Schultz, Peter Andrew

    2011-12-01

    The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. Achieving the objective of modeling the performance of a disposal scenario requires describing processes involved in waste form degradation and radionuclide release at the subcontinuum scale, beginning with mechanistic descriptions of chemical reactions and chemical kinetics at the atomic scale, and upscaling into effective, validated constitutive models for input to high-fidelity continuum scale codes for coupled multiphysics simulations of release and transport. Verification and validation (V&V) is required throughout the system to establish evidence-based metrics for the level of confidence in M&S codes and capabilities, including at the subcontiunuum scale and the constitutive models they inform or generate. This Report outlines the nature of the V&V challenge at the subcontinuum scale, an approach to incorporate V&V concepts into subcontinuum scale modeling and simulation (M&S), and a plan to incrementally incorporate effective V&V into subcontinuum scale M&S destined for use in the NEAMS Waste IPSC work flow to meet requirements of quantitative confidence in the constitutive models informed by subcontinuum scale phenomena.

  2. Verification and validation of the decision analysis model for assessment of tank waste remediation system waste treatment strategies

    SciTech Connect (OSTI)

    Awadalla, N.G.; Eaton, S.C.F.

    1996-09-04

    This document is the verification and validation final report for the Decision Analysis Model for Assessment of Tank Waste Remediation System Waste Treatment Strategies. This model is also known as the INSIGHT Model.

  3. Tank waste remediation system integrated technology plan. Revision 2

    SciTech Connect (OSTI)

    Eaton, B.; Ignatov, A.; Johnson, S.; Mann, M.; Morasch, L.; Ortiz, S.; Novak, P. [eds.] [Pacific Northwest Lab., Richland, WA (United States)

    1995-02-28

    The Hanford Site, located in southeastern Washington State, is operated by the US Department of Energy (DOE) and its contractors. Starting in 1943, Hanford supported fabrication of reactor fuel elements, operation of production reactors, processing of irradiated fuel to separate and extract plutonium and uranium, and preparation of plutonium metal. Processes used to recover plutonium and uranium from irradiated fuel and to recover radionuclides from tank waste, plus miscellaneous sources resulted in the legacy of approximately 227,000 m{sup 3} (60 million gallons) of high-level radioactive waste, currently in storage. This waste is currently stored in 177 large underground storage tanks, 28 of which have two steel walls and are called double-shell tanks (DSTs) an 149 of which are called single-shell tanks (SSTs). Much of the high-heat-emitting nuclides (strontium-90 and cesium-137) has been extracted from the tank waste, converted to solid, and placed in capsules, most of which are stored onsite in water-filled basins. DOE established the Tank Waste Remediation System (TWRS) program in 1991. The TWRS program mission is to store, treat, immobilize and dispose, or prepare for disposal, the Hanford tank waste in an environmentally sound, safe, and cost-effective manner. Technology will need to be developed or improved to meet the TWRS program mission. The Integrated Technology Plan (ITP) is the high-level consensus plan that documents all TWRS technology activities for the life of the program.

  4. Integrated Waste Management | Department of Energy

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverseIMPACT EVALUATION PLANIs gravity aOverviewISM Integrated SafetyCooling

  5. DOE complex buried waste characterization assessment. Buried Waste Integrated Demonstration Program

    SciTech Connect (OSTI)

    Kaae, P.S.; Holter, G.M.; Garrett, S.M.K.

    1993-01-01

    The work described in this report was conducted by Pacific Northwest Laboratory to provide information to the Buried Waste Integrated Demonstration (BWID) program. The information in this report is intended to provide a complex-wide planning base for th.e BWID to ensure that BWID activities are appropriately focused to address the range of remediation problems existing across the US Department of Energy (DOE) complex. This report contains information characterizing the 2.1 million m{sup 3} of buried and stored wastes and their associated sites at six major DOE facilities. Approximately 85% of this waste is low-level waste, with about 12% TRU or TRU mixed waste; the remaining 3% is low-level mixed waste. In addition, the report describes soil contamination sites across the complex. Some of the details that would be useful in further characterizing the buried wastes and contaminated soil sites across the DOE complex are either unavailable or difficult to locate. Several options for accessing this information and/or improving the information that is available are identified in the report. This document is a companion to Technology Needs for Remediation: Hanford and Other DOE Sites, PNL-8328 (Stapp 1993).

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

    SciTech Connect (OSTI)

    Not Available

    1992-04-01

    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.

  7. The Integrated Waste Tracking Systems (IWTS) - A Comprehensive Waste Management Tool

    SciTech Connect (OSTI)

    Robert S. Anderson

    2005-09-01

    The US Department of Energy (DOE) Idaho National Laboratory (INL) site located near Idaho Falls, ID USA, has developed a comprehensive waste management and tracking tool that integrates multiple operational activities with characterization data from waste declaration through final waste disposition. The Integrated Waste Tracking System (IWTS) provides information necessary to help facility personnel properly manage their waste and demonstrate a wide range of legal and regulatory compliance. As a client?server database system, the IWTS is a proven tracking, characterization, compliance, and reporting tool that meets the needs of both operations and management while providing a high level of flexibility. This paper describes some of the history involved with the development and current use of IWTS as a comprehensive waste management tool as well as a discussion of IWTS deployments performed by the INL for outside clients. Waste management spans a wide range of activities including: work group interactions, regulatory compliance management, reporting, procedure management, and similar activities. The IWTS documents these activities and performs tasks in a computer-automated environment. Waste characterization data, container characterization data, shipments, waste processing, disposals, reporting, and limit compliance checks are just a few of the items that IWTS documents and performs to help waste management personnel perform their jobs. Throughout most hazardous and radioactive waste generating, storage and disposal sites, waste management is performed by many different groups of people in many facilities. Several organizations administer their areas of waste management using their own procedures and documentation independent of other organizations. Files are kept, some of which are treated as quality records, others not as stringent. Quality records maintain a history of: changes performed after approval, the reason for the change(s), and a record of whom and when the changes were made. As regulations and permits change, and as the proliferation of personal computers flourish, procedures and data files begin to be stored in electronic databases. With many different organizations, contractors, and unique procedures, several dozen databases are used to track and maintain aspects of waste management. As one can see, the logistics of collecting and certifying data from all organizations to provide comprehensive information would not only take weeks to perform, but usually presents a variety of answers that require an immediate unified resolution. A lot of personnel time is spent scrubbing the data in order to determine the correct information. The issue of disparate data is a concern in itself, and is coupled with the costs associated with maintaining several separate databases. In order to gain waste management efficiencies across an entire facility or site, several waste management databases located among several organizations would need to be consolidated. The IWTS is a system to do just that, namely store and track containerized waste information for an entire site. The IWTS has proven itself at the INL since 1995 as an efficient, successful, time saving management tool to help meet the needs of both operations and management for hazardous and radiological containerized waste. Other sites have also benefited from IWTS as it has been deployed at West Valley Nuclear Services Company DOE site as well as Ontario Power Ge

  8. 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.

    1992-08-01

    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.

  9. 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.

    1992-01-01

    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.

  10. Low level mixed waste thermal treatment technical basis report

    SciTech Connect (OSTI)

    Place, B.G.

    1994-12-01

    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.

  11. Advanced Fuel Cycle Treatment, Recycling, and Disposal of Nuclear Waste

    SciTech Connect (OSTI)

    Collins, Emory D [ORNL; Jubin, Robert Thomas [ORNL; DelCul, Guillermo D [ORNL; Spencer, Barry B [ORNL; Renier, John-Paul [ORNL

    2009-01-01

    Nuclear waste, in the form of used and spent nuclear fuel, is currently being stored in the U.S., mostly at reactor sites to await future direct disposal or treatment to permit recycle of re-usable components and minimization of wastes requiring geologic disposal. The used fuel is currently accumulating at a rate of over 2,000 tons per year and a total of over 60,000 tons is in storage. New dry storage capacity is estimated to cost {approx} $0.6 B per year. Technologies have been developed and deployed worldwide to treat only a portion of the nuclear waste that is generated. Recent research, development, and systems analysis studies have shown that nuclear waste treatment could be done at the rate of generation in a safe, environmentally friendly, and cost-effective manner. These studies continue to show that major benefits can be obtained by allowing the used fuel assemblies to remain in safe storage for 30 years or longer before treatment. During this time, the radioactivity and decay heat generation decrease substantially, such that the separations process can be simplified and made less costly, waste gases containing {sup 85}Kr can be released below regulatory limits, and the solid fission product wastes containing {sup 137}Cs and {sup 90}Sr require decay storage for a much shorter time-period before geologic disposal. In addition, the need for separating curium from americium and for extra purification cycles for the uranium and uranium-plutonium-neptunium products is greatly diminished. Moreover, during the 30+ years of storage prior to treatment, the quality of the recyclable fuel is only degraded by less than 5 percent. The 30+ year storage period also enables recycle of long-lived transuranic actinides to be accomplished in existing light water reactors without waiting on and incurring the cost of the development, licensing, and deployment of future Gen IV reactors. Overall, the safety, environmental, and cost benefits of treating the longer aged used nuclear wastes are substantial.

  12. Implementation of Treatment Systems for Low and Intermediate Radioactive Waste at Site Radwaste Treatment Facility (SRTF), PR China - 12556

    SciTech Connect (OSTI)

    Lohmann, Peter; Nasarek, Ralph; Aign, Joerg

    2012-07-01

    The AP1000 reactors being built in the People's Republic of China require a waste treatment facility to process the low and intermediate radioactive waste produced by these nuclear power stations. Westinghouse Electric Germany GmbH was successful in being awarded a contract as to the planning, delivery and commissioning of such a waste treatment facility. The Site Radwaste Treatment Facility (SRTF) is a waste treatment facility that can meet the AP1000 requirements and it will become operational in the near future. The SRTF is situated at the location of Sanmen, People's Republic of China, next to one of the AP1000 and is an adherent building to the AP1000 comprising different waste treatment processes for radioactive spent filter cartridges, ion-exchange resins and radioactive liquid and solid waste. The final product of the SRTF-treatment is a 200 l drum with cemented waste or grouted waste packages for storage in a local storage facility. The systems used in the SRTF are developed for these special requirements, based on experience from similar systems in the German nuclear industry. The main waste treatment systems in the SRTF are: - Filter Cartridge Processing System (FCS); - HVAC-Filter and Solid Waste Treatment Systems (HVS); - Chemical Liquid Treatment Systems (CTS); - Spent Resin Processing Systems (RES); - Mobile Treatment System (MBS). (authors)

  13. Dewatering Treatment Scale-up Testing Results of Hanford Tank Wastes

    SciTech Connect (OSTI)

    Tedeschi, A.R.; May, T.H.; Bryan, W.E.

    2008-07-01

    This report documents CH2M HILL Hanford Group Inc. (CH2M HILL) 2007 dryer testing results in Richland, WA at the AMEC Nuclear Ltd., GeoMelt Division (AMEC) Horn Rapids Test Site. It provides a discussion of scope and results to qualify the dryer system as a viable unit-operation in the continuing evaluation of the bulk vitrification process. A 10,000 liter (L) dryer/mixer was tested for supplemental treatment of Hanford tank low activity wastes, drying and mixing a simulated non-radioactive salt solution with glass forming minerals. Testing validated the full scale equipment for producing dried product similar to smaller scale tests, and qualified the dryer system for a subsequent integrated dryer/vitrification test using the same simulant and glass formers. The dryer system is planned for installation at the Hanford tank farms to dry/mix radioactive waste for final treatment evaluation of the supplemental bulk vitrification process. (authors)

  14. DEWATERING TREATMENT SCALE-UP TESTING RESULTS OF HANFORD TANK WASTES

    SciTech Connect (OSTI)

    TEDESCHI AR

    2008-01-23

    This report documents CH2M HILL Hanford Group Inc. (CH2M HILL) 2007 dryer testing results in Richland, WA at the AMEC Nuclear Ltd., GeoMelt Division (AMEC) Horn Rapids Test Site. It provides a discussion of scope and results to qualify the dryer system as a viable unit-operation in the continuing evaluation of the bulk vitrification process. A 10,000 liter (L) dryer/mixer was tested for supplemental treatment of Hanford tank low-activity wastes, drying and mixing a simulated non-radioactive salt solution with glass forming minerals. Testing validated the full scale equipment for producing dried product similar to smaller scale tests, and qualified the dryer system for a subsequent integrated dryer/vitrification test using the same simulant and glass formers. The dryer system is planned for installation at the Hanford tank farms to dry/mix radioactive waste for final treatment evaluation of the supplemental bulk vitrification process.

  15. CLASSIFICATION OF THE MGR WASTE TREATMENT BUILDING VENTILATION SYSTEM

    SciTech Connect (OSTI)

    S.E. Salzman

    1999-08-31

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) waste treatment building ventilation system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998).

  16. Review of the integrated thermal and nonthermal treatment system studies. Final report

    SciTech Connect (OSTI)

    NONE

    1996-10-01

    This report contains a review and evaluation of three systems analysis studies performed by LITCO on integrated thermal treatment systems and integrated nonthermal treatment systems for the remediation of mixed low-level waste stored throughout the US Department of Energy weapons complex. The review was performed by an independent team of nine researchers from the Energy and Environmental Research Center, Science Applications International Corporation, the Waste Policy Institute, and Virginia Tech. The three studies reviewed were as follows: Integrated Thermal Treatment System Study, Phase 1 -- issued July 1994; Integrated Thermal Treatment System Study, Phase 2 -- issued February 1996; and Integrated Nonthermal Treatment System Study -- drafted March 1996. The purpose of this review was to (1) determine whether the assumptions of the studies were adequate to produce an unbiased review of both thermal and nonthermal systems, (2) to identify the critical areas of the studies that would benefit from further investigation, and (3) to develop a standard template that could be used in future studies to assure a sound application of systems engineering.

  17. Sodium Recycle Economics for Waste Treatment Plant Operations

    SciTech Connect (OSTI)

    Sevigny, Gary J.; Poloski, Adam P.; Fountain, Matthew S.

    2008-08-31

    Sodium recycle at the Hanford Waste Treatment Plant (WTP) would reduce the number of glass canisters produced, and has the potential to significantly reduce the cost to the U.S. Department of Energy (DOE) of treating the tank wastes by hundreds of millions of dollars. The sodium, added in the form of sodium hydroxide, was originally added to minimize corrosion of carbon-steel storage tanks from acidic reprocessing wastes. In the baseline Hanford treatment process, sodium hydroxide is required to leach gibbsite and boehmite from the high level waste (HLW) sludge. In turn, this reduces the amount of HLW glass produced. Currently, a significant amount of additional sodium hydroxide will be added to the process to maintain aluminate solubility at ambient temperatures during ion exchange of cesium. The vitrification of radioactive waste is limited by sodium content, and this additional sodium mass will increase low-activity waste-glass mass. An electrochemical salt-splitting process, based on sodium-ion selective ceramic membranes, is being developed to recover and recycle sodium hydroxide from high-salt radioactive tank wastes in DOE’s complex. The ceramic membranes are from a family of materials known as sodium (Na)—super-ionic conductors (NaSICON)—and the diffusion of sodium ions (Na+) is allowed, while blocking other positively charged ions. A cost/benefit evaluation was based on a strategy that involves a separate caustic-recycle facility based on the NaSICON technology, which would be located adjacent to the WTP facility. A Monte Carlo approach was taken, and several thousand scenarios were analyzed to determine likely economic results. The cost/benefit evaluation indicates that 10,000–50,000 metric tons (MT) of sodium could be recycled, and would allow for the reduction of glass production by 60,000–300,000 MT. The cost of the facility construction and operation was scaled to the low-activity waste (LAW) vitrification facility, showing cost would be roughly $150 million to $400 million for construction and $10 million to $40 million per year for operations. Depending on the level of aluminate supersaturation allowed in the storage tanks in the LAW Pretreatment Facility, these values indicate a return on investment of up to 25% to 60%.

  18. Systems approaches to integrated solid waste management in developing countries

    SciTech Connect (OSTI)

    Marshall, Rachael E.; Farahbakhsh, Khosrow

    2013-04-15

    Highlights: ? Five drivers led developed countries to current solid waste management paradigm. ? Many unique factors challenge developing country solid waste management. ? Limited transferability of developed country approaches to developing countries. ? High uncertainties and decision stakes call for post-normal approaches. ? Systems thinking needed for multi-scale, self-organizing eco-social waste systems. - Abstract: Solid waste management (SWM) has become an issue of increasing global concern as urban populations continue to rise and consumption patterns change. The health and environmental implications associated with SWM are mounting in urgency, particularly in the context of developing countries. While systems analyses largely targeting well-defined, engineered systems have been used to help SWM agencies in industrialized countries since the 1960s, collection and removal dominate the SWM sector in developing countries. This review contrasts the history and current paradigms of SWM practices and policies in industrialized countries with the current challenges and complexities faced in developing country SWM. In industrialized countries, public health, environment, resource scarcity, climate change, and public awareness and participation have acted as SWM drivers towards the current paradigm of integrated SWM. However, urbanization, inequality, and economic growth; cultural and socio-economic aspects; policy, governance, and institutional issues; and international influences have complicated SWM in developing countries. This has limited the applicability of approaches that were successful along the SWM development trajectories of industrialized countries. This review demonstrates the importance of founding new SWM approaches for developing country contexts in post-normal science and complex, adaptive systems thinking.

  19. Integrated solid waste management of Palm Beach County, Florida

    SciTech Connect (OSTI)

    1995-11-01

    The subject document reports the results of an in-depth investigation of the fiscal year 1992 cost of the Palm Beach County, Florida integrated municipal solid waste management system (IMSWMS), the energy consumed to operate the system, and the environmental performance requirements for each of the system`s waste-processing and disposal facilities. Actual data from records kept by participants is reported in this document. Every effort was made to minimize the use of assumptions, and no attempt is made to interpret the data reported. Analytical approaches are documented so that interested analysts may perform manipulation or further analysis of the data. As such, the report is a reference document for MSW management professionals who are interested in the actual costs and energy consumption for a one-year period, of an operating IMSWMS.

  20. Nuclear Energy Advanced Modeling and Simulation (NEAMS) Waste Integrated Performance and Safety Codes (IPSC) : FY10 development and integration.

    SciTech Connect (OSTI)

    Criscenti, Louise Jacqueline; Sassani, David Carl; Arguello, Jose Guadalupe, Jr.; Dewers, Thomas A.; Bouchard, Julie F.; Edwards, Harold Carter; Freeze, Geoffrey A.; Wang, Yifeng; Schultz, Peter Andrew

    2011-02-01

    This report describes the progress in fiscal year 2010 in developing the Waste Integrated Performance and Safety Codes (IPSC) in support of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The goal of the Waste IPSC is to develop an integrated suite of computational modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. Waste IPSC activities in fiscal year 2010 focused on specifying a challenge problem to demonstrate proof of concept, developing a verification and validation plan, and performing an initial gap analyses to identify candidate codes and tools to support the development and integration of the Waste IPSC. The current Waste IPSC strategy is to acquire and integrate the necessary Waste IPSC capabilities wherever feasible, and develop only those capabilities that cannot be acquired or suitably integrated, verified, or validated. This year-end progress report documents the FY10 status of acquisition, development, and integration of thermal-hydrologic-chemical-mechanical (THCM) code capabilities, frameworks, and enabling tools and infrastructure.

  1. Integrated beta and gamma radiation dose calculations for the ferrocyanide waste tanks

    SciTech Connect (OSTI)

    Parra, S.A.

    1994-11-30

    This report contains the total integrated beta and gamma radiation doses in all the ferrocyanide waste tanks. It also contains estimated gamma radiation dose rates for all single-shell waste tanks containing a liquid observation well.

  2. Secondary Low-Level Waste Treatment Strategy Analysis

    SciTech Connect (OSTI)

    D.M. LaRue

    1999-05-25

    The objective of this analysis is to identify and review potential options for processing and disposing of the secondary low-level waste (LLW) that will be generated through operation of the Monitored Geologic Repository (MGR). An estimate of annual secondary LLW is generated utilizing the mechanism established in ''Secondary Waste Treatment Analysis'' (Reference 8.1) and ''Secondary Low-Level Waste Generation Rate Analysis'' (Reference 8.5). The secondary LLW quantities are based on the spent fuel and high-level waste (HLW) arrival schedule as defined in the ''Controlled Design Assumptions Document'' (CDA) (Reference 8.6). This analysis presents estimates of the quantities of LLW in its various forms. A review of applicable laws, codes, and standards is discussed, and a synopsis of those applicable laws, codes, and standards and their impacts on potential processing and disposal options is presented. The analysis identifies viable processing/disposal options in light of the existing laws, codes, and standards, and then evaluates these options in regard to: (1) Process and equipment requirements; (2) LLW disposal volumes; and (3) Facility requirements.

  3. Energy implications of integrated solid waste management systems. Final report

    SciTech Connect (OSTI)

    Little, R.E.; McClain, G.; Becker, M.; Ligon, P.; Shapiro, K.

    1994-07-01

    This study develops estimates of energy use and recovery from managing municipal solid waste (MSW) under various collection, processing, and disposal scenarios. We estimate use and recovery -- or energy balance -- resulting from MSW management activities such as waste collection, transport, processing, and disposal, as well as indirect use and recovery linked to secondary materials manufacturing using recycled materials. In our analysis, secondary materials manufacturing displaces virgin materials manufacturing for 13 representative products. Energy implications are expressed as coefficients that measure the net energy saving (or use) of displacing products made from virgin versus recycled materials. Using data developed for the 1992 New York City Master Plan as a starting point, we apply our method to an analysis of various collection systems and 30 types of facilities to illustrate bow energy balances shift as management systems are modified. In sum, all four scenarios show a positive energy balance indicating the energy and advantage of integrated systems versus reliance on one or few technology options. That is, energy produced or saved exceeds the energy used to operate the solid waste system. The largest energy use impacts are attributable to processing, including materials separation and composting. Collection and transportation energy are relatively minor contributors. The largest two contributors to net energy savings are waste combustion and energy saved by processing recycled versus virgin materials. An accompanying spatial analysis methodology allocates energy use and recovery to New York City, New York State outside the city, the U.S., and outside the U.S. Our analytical approach is embodied in a spreadsheet model that can be used by energy and solid waste analysts to estimate impacts of management scenarios at the state and substate level.

  4. 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)

    2012-07-01

    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)

  5. Characterization of the solid low level mixed waste inventory for the solid waste thermal treatment activity - III

    SciTech Connect (OSTI)

    Place, B.G., Westinghouse Hanford

    1996-09-24

    The existing thermally treatable, radioactive mixed waste inventory is characterized to support implementation of the commercial, 1214 thermal treatment contract. The existing thermally treatable waste inventory has been identified using a decision matrix developed by Josephson et al. (1996). Similar to earlier waste characterization reports (Place 1993 and 1994), hazardous materials, radionuclides, physical properties, and waste container data are statistically analyzed. In addition, the waste inventory data is analyzed to correlate waste constituent data that are important to the implementation of the commercial thermal treatment contract for obtaining permits and for process design. The specific waste parameters, which were analyzed, include the following: ``dose equivalent`` curie content, polychlorinated biphenyl (PCB) content, identification of containers with PA-related mobile radionuclides (14C, 12 79Se, 99Tc, and U isotopes), tritium content, debris and non-debris content, container free liquid content, fissile isotope content, identification of dangerous waste codes, asbestos containers, high mercury containers, beryllium dust containers, lead containers, overall waste quantities, analysis of container types, and an estimate of the waste compositional split based on the thermal treatment contractor`s proposed process. A qualitative description of the thermally treatable mixed waste inventory is also provided.

  6. WASTE TREATMENT PLANT (WTP) LIQUID EFFLUENT TREATABILITY EVALUATION

    SciTech Connect (OSTI)

    LUECK, K.J.

    2004-10-18

    A forecast of the radioactive, dangerous liquid effluents expected to be produced by the Waste Treatment Plant (WTP) was provided by Bechtel National, Inc. (BNI 2004). The forecast represents the liquid effluents generated from the processing of Tank Farm waste through the end-of-mission for the WTP. The WTP forecast is provided in the Appendices. The WTP liquid effluents will be stored, treated, and disposed of in the Liquid Effluent Retention Facility (LERF) and the Effluent Treatment Facility (ETF). Both facilities are located in the 200 East Area and are operated by Fluor Hanford, Inc. (FH) for the US. Department of Energy (DOE). The treatability of the WTP liquid effluents in the LERF/ETF was evaluated. The evaluation was conducted by comparing the forecast to the LERF/ETF treatability envelope (Aromi 1997), which provides information on the items which determine if a liquid effluent is acceptable for receipt and treatment at the LERF/ETF. The format of the evaluation corresponds directly to the outline of the treatability envelope document. Except where noted, the maximum annual average concentrations over the range of the 27 year forecast was evaluated against the treatability envelope. This is an acceptable approach because the volume capacity in the LERF Basin will equalize the minimum and maximum peaks. Background information on the LERF/ETF design basis is provided in the treatability envelope document.

  7. Sodium-bearing Waste Treatment Technology Evaluation Report

    SciTech Connect (OSTI)

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

    2004-05-01

    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.

  8. Time and motion study for alternative mixed low-level waste treatment systems

    SciTech Connect (OSTI)

    Biagi, C.; Vetromile, J.; Teheranian, B.

    1997-02-01

    The time and motion study was developed to look at time-related aspects of the technologies and systems studied in the Integrated Thermal Treatment Systems (ITTS) and Integrated Nonthermal Treatment Systems (INTS) studies. The INTS and ITTS studies combined technologies into systems and subsystems for evaluation. The system approach provides DOE a method of measuring advantages and disadvantages of the many technologies currently being researched. For example, technologies which are more likely to create secondary waste or require extensive pretreatment handling may be less desirable than technologies which require less support from other processes. The time and motion study was designed to address the time element in the INTS and ITTS systems studies. Previous studies have focused on material balance, cost, technical effectiveness, regulatory issues, community acceptance, and operability. This study looks at system dynamics by estimating the treatment time required for a unit of waste, from receipt to certification for shipping. Labor estimates are also developed, based on the time required to do each task for each process. This focus on time highlights critical path processes and potential bottlenecks in the INTS and ITTS systems.

  9. Standard guide for characterization of radioactive and/or hazardous wastes for thermal treatment

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2003-01-01

    1.1 This guide identifies methods to determine the physical and chemical characteristics of radioactive and/or hazardous wastes before a waste is processed at high temperatures, for example, vitrification into a homogeneous glass ,glass-ceramic, or ceramic waste form. This includes waste forms produced by ex-situ vitrification (ESV), in-situ vitrification (ISV), slagging, plasma-arc, hot-isostatic pressing (HIP) and/or cold-pressing and sintering technologies. Note that this guide does not specifically address high temperature waste treatment by incineration but several of the analyses described in this guide may be useful diagnostic methods to determine incinerator off-gas composition and concentrations. The characterization of the waste(s) recommended in this guide can be used to (1) choose and develop the appropriate thermal treatment methodology, (2) determine if waste pretreatment is needed prior to thermal treatment, (3) aid in development of thermal treatment process control, (4) develop surrogate wa...

  10. Lessons Learned In Technology Development for Supplemental Treatment of Low-Activity Waste at Hanford

    SciTech Connect (OSTI)

    Biyani, R.K. [Washington State Department of Ecology, Richland, WA (United States)

    2008-07-01

    Hanford needs supplemental technology treatment of low-activity waste (LAW) in addition to the Waste Treatment Plant (WTP). The Washington State Department of Ecology requires that supplemental technology provide the same protection to human health and the environment as WTP LAW glass. In 2002, the U.S. Department of Energy (US DOE) evaluated supplemental treatment technologies for LAW treatment and looked more closely at three: bulk vitrification (BV), steam reforming, and tailored cementitious stabilization. US DOE with Ecology's support chose to design and test BV because it believed BV would offer rapid deployment, low cost, and waste stream versatility. This paper will describe the path taken in choosing and developing technologies for additional LAW treatment capacity and, more importantly, the lessons learned along the way. In conclusion: Contractors' off-the-shelf vitrification technology that worked elsewhere may not apply easily to Hanford's waste challenges. The BV development process could have been improved by first identifying and then focusing on primary areas of concern. Continuing integrated tests at the Horn Rapids facility offers a convenient option to test both the dryer and the SMF. But the plan for development of the SMF must be short term with well defined success criteria. US DOE has the responsibility to carefully evaluate each proposal and make critical decisions that will make optimum use of limited funds. The ERP provided valuable technical guidance on improving BV's design. This must be complemented by a similar study of cost effectiveness of a process. We must have a better understanding of life cycle costs before a path for supplemental treatment is chosen. US DOE has now gained five years of experience in developing BV. It is time for US DOE to make defensible economic evaluations before further funding towards developing supplemental treatment. It must reevaluate if the projected advantages of rapid deployment, low cost, and waste stream versatility are still valid. The decision-making methodology US DOE uses to approve designs as part of its Critical Decision Process appears rigorous and useful. Looking ahead, Ecology expects US DOE will use lessons learned from BV and other testing in a concerted manner as part of their decision-making process. The success of Hanford's cleanup depends on it. (authors)

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

    SciTech Connect (OSTI)

    Reidel, Steve P.

    2006-05-26

    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.

  12. 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)

    2013-07-01

    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)

  13. Tank waste remediation system optimized processing strategy with an altered treatment scheme

    SciTech Connect (OSTI)

    Slaathaug, E.J.

    1996-03-01

    This report provides an alternative strategy evolved from the current Hanford Site Tank Waste Remediation System (TWRS) programmatic baseline for accomplishing the treatment and disposal of the Hanford Site tank wastes. This optimized processing strategy with an altered treatment scheme performs the major elements of the TWRS Program, but modifies the deployment of selected treatment technologies to reduce the program cost. The present program for development of waste retrieval, pretreatment, and vitrification technologies continues, but the optimized processing strategy reuses a single facility to accomplish the separations/low-activity waste (LAW) vitrification and the high-level waste (HLW) vitrification processes sequentially, thereby eliminating the need for a separate HLW vitrification facility.

  14. CAST STONE TECHNOLOGY FOR TREATMENT & DISPOSAL OF IODINE RICH CAUSTIC WASTE DEMONSTRATION FINAL REPORT

    SciTech Connect (OSTI)

    LOCKREM, L.L.

    2005-07-14

    CH2M HILL is working to develop, design, and construct low-activity waste (LAW) treatment and imcholization systems to supplement the LAW capacity provided by the Waste Treatment and Immobilization Plant. CH2M HILL is investigating use of cast stone technology for treatment and immobilization of caustic solutions containing high concentrations of radioactive Iodine-129.

  15. Role Of Informal Solid Waste Management Sector And Possibilities Of Integration; The

    E-Print Network [OSTI]

    Columbia University

    Role Of Informal Solid Waste Management Sector And Possibilities Of Integration; The Case religion. Attracts tourist from all over the globe. #12;Municipal Solid Waste management : Current Formal;Social-Economic Vulnerability #12;Major Solid Waste management Options for the city Incineration based

  16. Integrated Waste Management in Sweden Where incineration is not a dirty word

    E-Print Network [OSTI]

    Columbia University

    Integrated Waste Management in Sweden Where incineration is not a dirty word As Toronto battles a lot from the Swedish approach to waste management. Sweden's view on basically all environmental to regional and local needs. The goal of waste management, in any country, should be to reduce the total

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

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  18. 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.

  19. Voluntary Protection Program Onsite Review, Advanced Mixed Waste Treatment Project- May 2009

    Broader source: Energy.gov [DOE]

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

  20. 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.

  1. Integrating treatment strategies for children with autism

    E-Print Network [OSTI]

    Jobin, Allison Brooke

    2012-01-01

    for teaching based on autism research. Austin: Pro-Ed.2010). Treatment approach, autism severity and interventionin young children. Research in Autism Spectrum Disorders, 4,

  2. A One System Integrated Approach to Simulant Selection for Hanford High Level Waste Mixing and Sampling Tests

    SciTech Connect (OSTI)

    Thien, Mike G. [Washington River Protection Solutions, LLC, Richland, WA (United States); Barnes, Steve M. [URS, Richland, WA (United States)

    2013-01-17

    The Hanford Tank Operations Contractor (TOC) and the Hanford Waste Treatment and Immobilization Plant (WTP) contractor are both engaged in demonstrating mixing, sampling, and transfer system capabilities using simulated Hanford High-Level Waste (HLW) formulations. This represents one of the largest remaining technical issues with the high-level waste treatment mission at Hanford. Previous testing has focused on very specific TOC or WTP test objectives and consequently the simulants were narrowly focused on those test needs. A key attribute in the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2010-2 is to ensure testing is performed with a simulant that represents the broad spectrum of Hanford waste. The One System Integrated Project Team is a new joint TOC and WTP organization intended to ensure technical integration of specific TOC and WTP systems and testing. A new approach to simulant definition has been mutually developed that will meet both TOC and WTP test objectives for the delivery and receipt of HLW. The process used to identify critical simulant characteristics, incorporate lessons learned from previous testing, and identify specific simulant targets that ensure TOC and WTP testing addresses the broad spectrum of Hanford waste characteristics that are important to mixing, sampling, and transfer performance are described.

  3. Mixed waste focus area integrated technical baseline report. Phase I, Volume 2: Revision 0

    SciTech Connect (OSTI)

    1996-01-16

    This document (Volume 2) contains the Appendices A through J for the Mixed Waste Focus Area Integrated Technical Baseline Report Phase I for the Idaho National Engineering Laboratory. Included are: Waste Type Managers` Resumes, detailed information on wastewater, combustible organics, debris, unique waste, and inorganic homogeneous solids and soils, and waste data information. A detailed list of technology deficiencies and site needs identification is also provided.

  4. Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants

    SciTech Connect (OSTI)

    Ross, W.A.; Schneider, K.J.; Swanson, J.L.; Yasutake, K.M.; Allen, R.P.

    1985-07-01

    This document provides a comparison of six treatment options for transuranic wastes (TRUW) resulting from the reprocessing of commercial spent fuel. Projected transuranic waste streams from the Barnwell Nuclear Fuel Plant (BNFP), the reference fuel reprocessing plant in this report, were grouped into the five categories of hulls and hardware, failed equipment, filters, fluorinator solids, and general process trash (GPT) and sample and analytical cell (SAC) wastes. Six potential treatment options were selected for the five categories of waste. These options represent six basic treatment objectives: (1) no treatment, (2) minimum treatment (compaction), (3) minimum number of processes and products (cementing or grouting), (4) maximum volume reduction without decontamination (melting, incinerating, hot pressing), (5) maximum volume reduction with decontamination (decontamination, treatment of residues), and (6) noncombustible waste forms (melting, incinerating, cementing). Schemes for treatment of each waste type were selected and developed for each treatment option and each type of waste. From these schemes, transuranic waste volumes were found to vary from 1 m/sup 3//MTU for no treatment to as low as 0.02 m/sup 3//MTU. Based on conceptual design requirements, life-cycle costs were estimated for treatment plus on-site storage, transportation, and disposal of both high-level and transuranic wastes (and incremental low-level wastes) from 70,000 MTU. The study concludes that extensive treatment is warranted from both cost and waste form characteristics considerations, and that the characteristics of most of the processing systems used are acceptable. The study recommends that additional combinations of treatment methods or strategies be evaluated and that in the interim, melting, incineration, and cementing be further developed for commercial TRUW. 45 refs., 9 figs., 32 tabs.

  5. 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.

    1990-09-18

    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.

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

    SciTech Connect (OSTI)

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

    1984-03-23

    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.

  7. Options assessment report: Treatment of nitrate salt waste at Los Alamos National Laboratory

    SciTech Connect (OSTI)

    Robinson, Bruce Alan; Stevens, Patrice Ann

    2015-09-16

    This report documents the methodology used to select a method of treatment for the remediated nitrate salt (RNS) and unremediated nitrate salt (UNS) waste containers at Los Alamos National Laboratory (LANL). The method selected should treat the containerized waste in a manner that renders the waste safe and suitable for transport and final disposal in the Waste Isolation Pilot Plant (WIPP) repository, under specifications listed in the WIPP Waste Acceptance Criteria (DOE/CBFO, 2013). LANL recognized that the results must be thoroughly vetted with the New Mexico Environment Department (NMED) and the a modification to the LANL Hazardous Waste Facility Permit is a necessary step before implementation of this or any treatment option. Likewise, facility readiness and safety basis approvals must be received from the Department of Energy (DOE). This report presents LANL's preferred option, and the documentation of the process for reaching the recommended treatment option for RNS and UNS waste, and is presented for consideration by NMED and DOE.

  8. Evaluation Of The Integrated Solubility Model, A Graded Approach For Predicting Phase Distribution In Hanford Tank Waste

    SciTech Connect (OSTI)

    Pierson, Kayla L.; Belsher, Jeremy D.; Seniow, Kendra R.

    2012-10-19

    The mission of the DOE River Protection Project (RPP) is to store, retrieve, treat and dispose of Hanford's tank waste. Waste is retrieved from the underground tanks and delivered to the Waste Treatment and Immobilization Plant (WTP). Waste is processed through a pretreatment facility where it is separated into low activity waste (LAW), which is primarily liquid, and high level waste (HLW), which is primarily solid. The LAW and HLW are sent to two different vitrification facilities and glass canisters are then disposed of onsite (for LAW) or shipped off-site (for HLW). The RPP mission is modeled by the Hanford Tank Waste Operations Simulator (HTWOS), a dynamic flowsheet simulator and mass balance model that is used for mission analysis and strategic planning. The integrated solubility model (ISM) was developed to improve the chemistry basis in HTWOS and better predict the outcome of the RPP mission. The ISM uses a graded approach to focus on the components that have the greatest impact to the mission while building the infrastructure for continued future improvement and expansion. Components in the ISM are grouped depending upon their relative solubility and impact to the RPP mission. The solubility of each group of components is characterized by sub-models of varying levels of complexity, ranging from simplified correlations to a set of Pitzer equations used for the minimization of Gibbs Energy.

  9. MEASUREMENT AND MODELLING OF AMMONIA EMISSIONS AT WASTE TREATMENT LAGOON-ATMOSPHERIC INTERFACE

    E-Print Network [OSTI]

    Aneja, Viney P.

    . Keywords: ammonia, emission, mass transfer, modelling, swine waste storage and treatment system 1MEASUREMENT AND MODELLING OF AMMONIA EMISSIONS AT WASTE TREATMENT LAGOON-ATMOSPHERIC INTERFACE of ammonia are approximately 75 Tg N/yr (1 Tg = 1012g). The major global source is excreta from domestic

  10. INTEGRATED POWER GENERATION SYSTEMS FOR COAL MINE WASTE METHANE UTILIZATION

    SciTech Connect (OSTI)

    Peet M. Soot; Dale R. Jesse; Michael E. Smith

    2005-08-01

    An integrated system to utilize the waste coal mine methane (CMM) at the Federal No. 2 Coal Mine in West Virginia was designed and built. The system includes power generation, using internal combustion engines, along with gas processing equipment to upgrade sub-quality waste methane to pipeline quality standards. The power generation has a nominal capacity of 1,200 kw and the gas processing system can treat about 1 million cubic feet per day (1 MMCFD) of gas. The gas processing is based on the Northwest Fuel Development, Inc. (NW Fuel) proprietary continuous pressure swing adsorption (CPSA) process that can remove nitrogen from CMM streams. The two major components of the integrated system are synergistic. The byproduct gas stream from the gas processing equipment can be used as fuel for the power generating equipment. In return, the power generating equipment provides the nominal power requirements of the gas processing equipment. This Phase III effort followed Phase I, which was comprised of a feasibility study for the project, and Phase II, where the final design for the commercial-scale demonstration was completed. The fact that NW Fuel is desirous of continuing to operate the equipment on a commercial basis provides the validation for having advanced the project through all of these phases. The limitation experienced by the project during Phase III was that the CMM available to operate the CPSA system on a commercial basis was not of sufficiently high quality. NW Fuel's CPSA process is limited in its applicability, requiring a relatively high quality of gas as the feed to the process. The CPSA process was demonstrated during Phase III for a limited time, during which the processing capabilities met the expected results, but the process was never capable of providing pipeline quality gas from the available low quality CMM. The NW Fuel CPSA process is a low-cost ''polishing unit'' capable of removing a few percent nitrogen. It was never intended to process CMM streams containing high levels of nitrogen, as is now the case at the Federal No.2 Mine. Even lacking the CPSA pipeline delivery demonstration, the project was successful in laying the groundwork for future commercial applications of the integrated system. This operation can still provide a guide for other coal mines which need options for utilization of their methane resources. The designed system can be used as a complete template, or individual components of the system can be segregated and utilized separately at other mines. The use of the CMM not only provides an energy fuel from an otherwise wasted resource, but it also yields an environmental benefit by reducing greenhouse gas emissions. The methane has twenty times the greenhouse effect as compared to carbon dioxide, which the combustion of the methane generates. The net greenhouse gas emission mitigation is substantial.

  11. A preliminary evaluation of alternatives for treatment of INEL Low-Level Waste and low-level mixed waste

    SciTech Connect (OSTI)

    Smith, T.H.; Roesener, W.S.; Jorgensen-Waters, M.J.; Edinborough, C.R.

    1992-06-01

    The Mixed and Low-Level Waste Treatment Facility (MLLWTF) project was established in 1991 by the US Department of Energy Idaho Field Office to provide treatment capabilities for Idaho National Engineering Laboratory (INEL) low-level mixed waste and low-level waste. This report identifies and evaluates the alternatives for treating that waste. Twelve treatment alternatives, ranging from ``no-action`` to constructing and operating the MLLWTF, are identified and evaluated. Evaluations include facility performance, environmental, safety, institutional, schedule, and rough order-of-magnitude cost comparisons. The performance of each alternative is evaluated against lists of ``musts`` and ``wants.`` Also included is a discussion of other key considerations for decision making. Analysis of results indicated further study is necessary to obtain the best estimate of future waste volumes and characteristics from the expanded INEL Decontamination and Decommissioning Program. It is also recommended that conceptual design begin as scheduled on the MLLWTF, maximum treatment alternative while re-evaluating the waste volume projections.

  12. Idaho's Advanced Mixed Waste Treatment Project Details 2013Accomplish...

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

    Articles A product drum of mixed low-level waste is lowered into a high-density polyethylene macro-pack. Innovative Technique Accelerates Waste Disposal at Idaho Site Only the...

  13. Waste treatment by reverse osmosis and membrane processing. (Latest citations from the NTIS Bibliographic database). Published Search

    SciTech Connect (OSTI)

    Not Available

    1994-11-01

    The bibliography contains citations concerning the technology of reverse osmosis and membrane processing in sewage and industrial waste treatment. Citations discuss ultrafiltration, industrial water reuse, hazardous waste treatment, municipal wastes, and materials recovery. Waste reduction and recycling in electroplating, metal finishing, and circuit board manufacturing are considered. (Contains 250 citations and includes a subject term index and title list.)

  14. Waste treatment by reverse osmosis and membrane processing. (Latest citations from the NTIS bibliographic database). Published Search

    SciTech Connect (OSTI)

    Not Available

    1994-03-01

    The bibliography contains citations concerning the technology of reverse osmosis and membrane processing in sewage and industrial waste treatment. Citations discuss ultrafiltration, industrial water reuse, hazardous waste treatment, municipal wastes, and materials recovery. Waste reduction and recycling in electroplating, metal finishing, and circuit board manufacturing are considered. (Contains a minimum of 245 citations and includes a subject term index and title list.)

  15. Feynman integral treatment of the Bargmann potential

    SciTech Connect (OSTI)

    Diaf, A.; Chouchaoui, A. . E-mail: akchouchaoui@yahoo.fr; Lombard, R.J.

    2005-06-01

    A method based on path integral formulation is given for obtaining exact solution of the s states for the Bargmann potentialV(r)=1ka{sup 2}{beta}({beta}-1)e{sup -2r/a}1-e{sup -r/a2}-Ae{sup -r/a}1-e{sup -r=} /{sup a},where {beta} and k are parameters. The exact energy spectrum and the normalised s-state eigenfunctions are obtained from the poles of the Green function and their residues, respectively. The results are compared with their of Schrodinger formalism, special cases are also discussed.

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

    SciTech Connect (OSTI)

    JOHNSTON GA

    2008-01-15

    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

  17. DEVELOPMENT OF THE BULK VITRIFICATION TREATMENT PROCESS FOR THE LOW ACTIVITY FRACTION OF HANFORD SINGLE SHELL TANK WASTES

    SciTech Connect (OSTI)

    Thompson, L.E.; Lowery, P.S.; Arrowsmith, H.W.; Snyder, T.; McElroy, J.L.

    2003-02-27

    AMEC Earth & Environmental, Inc. and RWE NUKEM Corporation have teamed to develop and apply a waste pre-treatment and bulk vitrification process for low activity waste (LAW) from Hanford Single Shell Tanks (SSTs). The pretreatment and bulk vitrification process utilizes technologies that have been successfully deployed to remediate both radioactive and chemically hazardous wastes at nuclear power plants, DOE sites, and commercial waste sites in the US and abroad. The process represents an integrated systems approach. The proposed AMEC/NUKEM process follow the extraction and initial segregation activities applied to the tank wastes carried out by others. The first stage of the process will utilize NUKEM's concentrate dryer (CD) system to concentrate the liquid waste stream. The concentrate will then be mixed with soil or glass formers and loaded into refractory-lined steel containers for bulk vitrification treatment using AMEC's In-Container Vitrification (ICV) process. Following the vitrification step, a lid will be placed on the container of cooled, solidified vitrified waste, and the container transported to the disposal site. The container serves as the melter vessel, the transport container and the disposal container. AMEC and NUKEM participated in the Mission Acceleration Initiative Workshop held in Richland, Washington in April 2000 [1]. An objective of the workshop was to identify selected technologies that could be combined into viable treatment options for treatment of the LAW fraction from selected Hanford waste tanks. AMEC's ICV process combined with NUKEM's CD system and other remote operating capabilities were presented as an integrated solution. The Team's proposed process received some of the highest ratings from the Workshop's review panel. The proposed approach compliments the Hanford Waste Treatment Plant (WTP) by reducing the amount of waste that the WTP would have to process. When combined with the capabilities of the WTP, the proposed approach will accelerate the tank waste remediation program plan and facilitate meeting the regulatory requirements for the remediation of the Hanford tank wastes. Consequently, the DOE Office of River Protection and CH2MHill Hanford Group identified bulk vitrification as one of the technologies to be investigated in FY03 through a demonstration program [2]. In October 2002, CH2MHill issued a request for proposal for the process development testing, engineering and data package for a non-radioactive (cold) pilot bulk vitrification process, and pre-conceptual engineering of a production bulk vitrification system. With AMEC in the lead, AMEC and NUKEM responded with a proposal. Pacific Northwest National Laboratory (PNNL) will support the proposed project as a key subcontractor by providing equipment, facilities, and personnel to support small-scale testing, including the testing on samples of actual tank wastes. This paper will provide an overview of the pre-treatment and bulk vitrification process, summarize the technical benefits the approach offers, and describe the demonstration program that has been developed for the project.

  18. 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.

    2014-01-27

    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

  19. 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)

    2006-07-01

    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)

  20. 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.

    2012-02-02

    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.

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

    SciTech Connect (OSTI)

    Not Available

    1987-11-01

    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.

  2. Radioactive Liquid Waste Treatment Facility Discharges in 2011

    SciTech Connect (OSTI)

    Del Signore, John C.

    2012-05-16

    This report documents radioactive discharges from the TA50 Radioactive Liquid Waste Treatment Facilities (RLWTF) during calendar 2011. During 2011, three pathways were available for the discharge of treated water to the environment: discharge as water through NPDES Outfall 051 into Mortandad Canyon, evaporation via the TA50 cooling towers, and evaporation using the newly-installed natural-gas effluent evaporator at TA50. Only one of these pathways was used; all treated water (3,352,890 liters) was fed to the effluent evaporator. The quality of treated water was established by collecting a weekly grab sample of water being fed to the effluent evaporator. Forty weekly samples were collected; each was analyzed for gross alpha, gross beta, and tritium. Weekly samples were also composited at the end of each month. These flow-weighted composite samples were then analyzed for 37 radioisotopes: nine alpha-emitting isotopes, 27 beta emitters, and tritium. These monthly analyses were used to estimate the radioactive content of treated water fed to the effluent evaporator. Table 1 summarizes this information. The concentrations and quantities of radioactivity in Table 1 are for treated water fed to the evaporator. Amounts of radioactivity discharged to the environment through the evaporator stack were likely smaller since only entrained materials would exit via the evaporator stack.

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

    SciTech Connect (OSTI)

    Brouns, Thomas M.

    2007-07-15

    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.

  4. Medium term municipal solid waste generation prediction by autoregressive integrated moving average

    SciTech Connect (OSTI)

    Younes, Mohammad K.; Nopiah, Z. M.; Basri, Noor Ezlin A.; Basri, Hassan

    2014-09-12

    Generally, solid waste handling and management are performed by municipality or local authority. In most of developing countries, local authorities suffer from serious solid waste management (SWM) problems and insufficient data and strategic planning. Thus it is important to develop robust solid waste generation forecasting model. It helps to proper manage the generated solid waste and to develop future plan based on relatively accurate figures. In Malaysia, solid waste generation rate increases rapidly due to the population growth and new consumption trends that characterize the modern life style. This paper aims to develop monthly solid waste forecasting model using Autoregressive Integrated Moving Average (ARIMA), such model is applicable even though there is lack of data and will help the municipality properly establish the annual service plan. The results show that ARIMA (6,1,0) model predicts monthly municipal solid waste generation with root mean square error equals to 0.0952 and the model forecast residuals are within accepted 95% confident interval.

  5. Integration of a Process Waste Gas into a Site's Energy Concept 

    E-Print Network [OSTI]

    Peterson, J.

    2000-01-01

    cogeneration system since 1985 so they naturally reviewed the economics of another such installation. At the same time, a new Acetylene plant was being planned, which generated a large process waste gas stream. Conceptual studies indicated that integrating...

  6. DEMONSTRATION OF SIMULATED WASTE TRANSFERS FROM TANK AY-102 TO THE HANFORD WASTE TREATMENT FACILITY

    SciTech Connect (OSTI)

    Adamson, D.; Poirier, M.; Steeper, T.

    2009-12-03

    In support of Hanford's AY-102 Tank waste certification and delivery of the waste to the Waste Treatment and Immobilization Plant (WTP), Savannah River National Laboratory (SRNL) was tasked by the Washington River Protection Solutions (WRPS) to evaluate the effectiveness of mixing and transferring the waste in the Double Shell Tank (DST) to the WTP Receipt Tank. This work is a follow-on to the previous 'Demonstration of Internal Structures Impacts on Double Shell Tank Mixing Effectiveness' task conducted at SRNL 1. The objective of these transfers was to qualitatively demonstrate how well waste can be transferred out of a mixed DST tank and to provide insights into the consistency between the batches being transferred. Twelve (12) different transfer demonstrations were performed, varying one parameter at a time, in the Batch Transfer Demonstration System. The work focused on visual comparisons of the results from transferring six batches of slurry from a 1/22nd scale (geometric by diameter) Mixing Demonstration Tank (MDT) to six Receipt Tanks, where the consistency of solids in each batch could be compared. The simulant used in this demonstration was composed of simulated Hanford Tank AZ-101 supernate, gibbsite particles, and silicon carbide particles, the same simulant/solid particles used in the previous mixing demonstration. Changing a test parameter may have had a small impact on total solids transferred from the MDT on a given test, but the data indicates that there is essentially no impact on the consistency of solids transferred batch to batch. Of the multiple parameters varied during testing, it was found that changing the nozzle velocity of the Mixer Jet Pumps (MJPs) had the biggest impact on the amount of solids transferred. When the MJPs were operating at 8.0 gpm (22.4 ft/s nozzle velocity, U{sub o}D=0.504 ft{sup 2}/s), the solid particles were more effectively suspended, thus producing a higher volume of solids transferred. When the MJP flow rate was reduced to 5 gpm (14 ft/s nozzle velocity, U{sub o}D = 0.315 ft{sup 2}/s) to each pump, dead zones formed in the tank, resulting in fewer solids being transferred in each batch to the Receipt Tanks. The larger, denser particles were displaced (preferentially to the smaller particles) to one of the two dead zones and not re-suspended for the duration of the test. As the liquid level dropped in the MDT, re-suspending the particles became less effective (6th batch). The poor consistency of the solids transferred in the 6th batch was due to low liquid level in the MDT, thus poor mixing by the MJPs. Of the twelve tests conducted the best transfer of solids occurred during Test 6 and 8 where the MJP rotation was reduced to 1.0 rpm.

  7. Mixed Waste Treatment Cost Analysis for a Range of GeoMelt Vitrification Process Configurations

    SciTech Connect (OSTI)

    Thompson, L. E.

    2002-02-27

    GeoMelt is a batch vitrification process used for contaminated site remediation and waste treatment. GeoMelt can be applied in several different configurations ranging from deep subsurface in situ treatment to aboveground batch plants. The process has been successfully used to treat a wide range of contaminated wastes and debris including: mixed low-level radioactive wastes; mixed transuranic wastes; polychlorinated biphenyls; pesticides; dioxins; and a range of heavy metals. Hypothetical cost estimates for the treatment of mixed low-level radioactive waste were prepared for the GeoMelt subsurface planar and in-container vitrification methods. The subsurface planar method involves in situ treatment and the in-container vitrification method involves treatment in an aboveground batch plant. The projected costs for the subsurface planar method range from $355-$461 per ton. These costs equate to 18-20 cents per pound. The projected cost for the in-container method is $1585 per ton. This cost equates to 80 cents per pound. These treatment costs are ten or more times lower than the treatment costs for alternative mixed waste treatment technologies according to a 1996 study by the US Department of Energy.

  8. Hanford Tank Waste Retrieval, Treatment and Disposition Framework...

    Office of Environmental Management (EM)

    the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's...

  9. Hanford Waste Treatment Plant completes critical system design...

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

    trips. They are scheduled to arrive later this fall. "The LAW melters are the largest waste-processing melters ever built, and there's been considerable work dedicated to...

  10. DOE Issues Draft RFP for Waste Treatment Services | Department...

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

    Restricted and Unrestricted RecyclingReuse, Low Activity Waste (LAW) Services, Ancillary Services, and support in establishing authorized release limits. This requirement...

  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. Part 1, Waste streams and treatment technologies

    SciTech Connect (OSTI)

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

    1992-09-01

    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. High-Level Liquid Waste Tank Integrity Workshop - 2008

    Office of Environmental Management (EM)

    techniques for primarysecondary tank wall and concrete * * Develop tank integrity roadmap and execution plan Develop tank integrity roadmap and execution plan including...

  13. Asit Nema\\Foundation Green-Ensys 1 RISK FACTORS ASSOCIATED WITH SOLID WASTE TREATMENT

    E-Print Network [OSTI]

    Columbia University

    to closure of the facilities within a rather short period after commissioning. Key Words MSW treatment, waste to energy/wealth, entropy, risk factors, landfill. INTRODUCTION A case study of 11 municipal solid waste landfill facility. Among the composting plants three were running at varying levels of capacity utilisation

  14. Project Execution Plan for the River Protection Project Waste Treatment & Immobilization Plant

    SciTech Connect (OSTI)

    MELLINGER, G.B.

    2003-05-03

    The Waste Treatment and Immobilization Plant (WTP), Project W-530, is the cornerstone in the mission of the Hanford Site's cleanup of more than 50 million gallons of highly toxic, high-level radioactive waste contained in aging underground storage tanks.

  15. Characterization of atmospheric ammonia emissions from swine waste storage and treatment lagoons

    E-Print Network [OSTI]

    Aneja, Viney P.

    Characterization of atmospheric ammonia emissions from swine waste storage and treatment lagoons, North Carolina State University, Raleigh Abstract. Fluxes of atmospheric ammonia-nitrogen (NH3-N, where NH3-N (14/17)NH3) from an anaerobic 2.5 ha (1 ha 10,000 m2 ) commercial hog waste storage lagoon were

  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 draft environmental impact 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. Water treatment capacity of forward osmosis systems utilizing power plant waste heat

    SciTech Connect (OSTI)

    Zhou, Xingshi; Gingerich, Daniel B.; Mauter, Meagan S.

    2015-06-11

    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.

  18. 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.

    2015-06-11

    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

  19. Biological Information Document, Radioactive Liquid Waste Treatment Facility

    SciTech Connect (OSTI)

    Biggs, J.

    1995-12-31

    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.

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

    SciTech Connect (OSTI)

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

    1995-01-01

    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.

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

    SciTech Connect (OSTI)

    Rohay, Alan C.; Reidel, Steve P.

    2005-02-24

    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.

  2. 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...

  3. 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.

  4. A Strategy to Assess Performance of Selected Low-Activity Waste Forms in an Integrated Disposal Facility

    SciTech Connect (OSTI)

    McGrail, B PETER.; Bacon, Diana H.; Serne, R JEFFREY.; Pierce, Eric M.

    2003-08-22

    An overall strategy for evaluating the long-term performance of three waste forms being considered for supplemental treatment of low-activity waste at Hanford is discussed. The same computational framework used to conduct the 2001 ILAW performance assessment will be used for all three waste forms. Cast stone will be modeled with a diffusion-advection transport model and bulk vitrified glass and steam reformed LAW will be modeled with a reactive chemical transport simulator. The recommended laboratory testing to support the supplemental LAW form selection includes single-pass flow-through (SPFT), product consistency (PCT), and vapor hydration tests for glass, SPFT and PCT tests for steam reformed LAW forms, and ANS 16.1 tests for cast stone. These and potentially other laboratory tests for the selected waste form(s) would also be the basis for more detailed studies needed to support a comprehensive long-term performance assessment should one or more of these waste forms be selected for disposal in an integrated disposal facility.

  5. RDX degradation using an integrated Fe(0)-microbial treatment approach

    E-Print Network [OSTI]

    Alvarez, Pedro J.

    RDX degradation using an integrated Fe(0)-microbial treatment approach M.J. Wildman and P was enhanced by anaerobic bacteria that feed on cathodic hydrogen (i.e., H2 produced during anaerobic Fe(0) corrosion by water). Apparently, the hydrogenotrophic consortium that exploits Fe(0) corrosion

  6. RDX degradation using an integrated Fe(0)-microbial treatment approach

    E-Print Network [OSTI]

    Alvarez, Pedro J.

    RDX degradation using an integrated Fe(0)-microbial treatment approach M.J. Wildman and P recalci- trance to microbial degradation, low volatility (dimensionless Henry's constant, H' = 2 × 10 attractive for in situ remedia- tion in that they conserve energy and water, and through long-term low

  7. U.S. Department of Energy (DOE) initiated performance enhancements to the Hanford waste treatment and immobilization plant (WTP) high-level waste vitrification (HLW) system

    SciTech Connect (OSTI)

    Bowan, Bradley [Energy Solutions, LLC (United States); Gerdes, Kurt [United States Department of Energy (United States); Pegg, Ian [Vitreous State Laboratory, Catholic University of America, 400 Hannan Hall 620 Michigan Avenue, NE Washington, DC 20064 (United States); Holton, Langdon [Pacific Northwest National Laboratory, PO Box 999, Richland WA 99352 (United States)

    2007-07-01

    Available in abstract form only. Full text of publication follows: The U.S Department of Energy is currently constructing, at the Hanford, Washington Site, a Waste Treatment and Immobilization Plant (WTP) for the treatment and immobilization, by vitrification, of stored underground tank wastes. The WTP is comprised of four major facilities: a Pretreatment facility to separate the tank waste into high level waste (HLW) and low activity waste (LAW); a HLW vitrification facility to immobilize the HLW fraction; a LAW vitrification facility to immobilize the LAW fraction and an analytical Laboratory to support the treatment facilities. DOE has strategic objectives to optimize the performance of the WTP facilities, and waste forms, in order to reduce the overall schedule and cost for the treatment of the Hanford tank wastes. One key part of this strategy is to maximize the loading of inorganic waste components in the final glass product (waste loading). For the Hanford tank wastes, this is challenging because of the compositional diversity of the wastes generated over several decades. This paper presents the results of an initial series of HLW waste loading enhancement tests, using diverse HLW compositions that are projected for treatment at the WTP. Specifically, results of glass formulation development and melter testing with simulated Hanford HLW containing high concentrations of troublesome components such as bismuth, aluminum, aluminum-sodium, and chromium will be presented. (authors)

  8. Pyrolysis Autoclave Technology Demonstration Program for Treatment of DOE Solidified Organic Wastes

    SciTech Connect (OSTI)

    Roesener, W.S.; Mason, J.B.; Ryan, K.; Bryson, S.; Eldredge, H.B.

    2006-07-01

    In the summer of 2005, MSE Technologies Applications, Inc. (MSE) and THOR Treatment Technologies, LLC (TTT) conducted a demonstration test of the Thermal Organic Reduction (THOR{sup sm}) in-drum pyrolysis autoclave system under contract to the Department of Energy. The purpose of the test was to demonstrate that the THOR{sup sm} pyrolysis autoclave system could successfully treat solidified organic waste to remove organics from the waste drums. The target waste was created at Rocky Flats and currently resides at the Radioactive Waste Management Complex (RWMC) at the Idaho National Laboratory (INL). Removing the organics from these drums would allow them to be shipped to the Waste Isolation Pilot Plant for disposal. Two drums of simulated organic setup waste were successfully treated. The simulated waste was virtually identical to the expected waste except for the absence of radioactive components. The simulated waste included carbon tetrachloride, trichloroethylene, perchloroethylene, Texaco Regal oil, and other organics mixed with calcium silicate and Portland cement stabilization agents. The two-stage process consisted of the THOR{sup sm} electrically heated pyrolysis autoclave followed by the MSE off gas treatment system. The treatment resulted in a final waste composition that meets the requirements for WIPP transportation and disposal. There were no detectable volatile organic compounds in the treated solid residues. The destruction and removal efficiency (DRE) for total organics in the two drums ranged from >99.999% to >99.9999%. The operation of the process proved to be easily controllable using the pyrolysis autoclave heaters. Complete treatment of a fully loaded surrogate waste drum including heat-up and cooldown took place over a two-day period. This paper discusses the results of the successful pyrolysis autoclave demonstration testing. (authors)

  9. Waste treatment by dialysis. (Latest citations from Pollution abstracts). Published Search

    SciTech Connect (OSTI)

    NONE

    1996-02-01

    The bibliography contains citations concerning the use of dialysis in the treatment of wastewaters. Techniques for the removal of metals, ammonia, waste acids, nitrates, and phosphates are described. Special attention is given to the desalination of liquid wastes. Applications of this technology to the treatment of effluent from the agrochemical, petrochemical, tanning, and electroplating industries are discussed. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

  10. Waste treatment by dialysis. (Latest citations from Pollution abstracts). Published Search

    SciTech Connect (OSTI)

    NONE

    1995-01-01

    The bibliography contains citations concerning the use of dialysis in the treatment of wastewaters. Techniques for the removal of metals, ammonia, waste acids, nitrates, and phosphates are described. Special attention is given to the desalination of liquid wastes. Applications of this technology to the treatment of effluent from the agrochemical, petrochemical, tanning, and electroplating industries are discussed. (Contains a minimum of 60 citations and includes a subject term index and title list.)

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

    E-Print Network [OSTI]

    Davol, Phebe

    1987-01-01

    compounds in the environment. Dibble and Bartha (1979) observed an increase in concentration of condensed ring fractions as oily wastes degrade in soil. The accumulation of PNAs in the soil at a land treatment facility is of concern since many... pentachlorophenol and creosote as preservative agents. The effluent from the treatment process was pumped from a concrete storage basin to a large lagoon where the solids were allowed to settle while the liquids evaporated. At the ti me the waste was collected...

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

    SciTech Connect (OSTI)

    Tolvanen, Outi K. . E-mail: outolvan@bytl.jyu.fi; Haenninen, Kari I.

    2006-07-01

    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.

  13. 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)

    1994-01-01

    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.

  14. Treatment of Asbestos Wastes Using the GeoMelt Vitrification Process

    SciTech Connect (OSTI)

    Finucane, K.G. [AMEC Nuclear Holdings Ltd., GeoMelt Div., Richland, WA (United States); Thompson, L.E. [Capto Group LLC, Dallas, TX (United States); Abuku, T. [ISV Japan Ltd., Yokohama-city (Japan); Nakauchi, H. [Mie Chuo Kaihatsu Co. Ltd., Hachiya, Iga City (Japan)

    2008-07-01

    The disposal of waste asbestos from decommissioning activities is becoming problematic in countries which have limited disposal space. A particular challenge is the disposal of asbestos wastes from the decommissioning of nuclear sites because some of it is radioactively contaminated or activated and disposal space for such wastes is limited. GeoMelt{sup R} vitrification is being developed as a treatment method for volume and toxicity minimization and radionuclide immobilization for UK radioactive asbestos mixed waste. The common practice to date for asbestos wastes is disposal in licensed landfills. In some cases, compaction techniques are used to minimize the disposal space requirements. However, such practices are becoming less practical. Social pressures have resulted in changes to disposal regulations which, in turn, have resulted in the closure of some landfills and increased disposal costs. In the UK, tens of thousands of tonnes of asbestos waste will result from the decommissioning of nuclear sites over the next 20 years. In Japan, it is estimated that over 40 million tonnes of asbestos materials used in construction will require disposal. Methods for the safe and cost effective volume reduction of asbestos wastes are being evaluated for many sites. The GeoMelt{sup R} vitrification process is being demonstrated at full-scale in Japan for the Japan Ministry of Environment and plans are being developed for the GeoMelt treatment of UK nuclear site decommissioning-related asbestos wastes. The full-scale treatment operations in Japan have also included contaminated soils and debris. The GeoMelt{sup R} vitrification process result in the maximum possible volume reduction, destroys the asbestos fibers, treats problematic debris associated with asbestos wastes, and immobilizes radiological contaminants within the resulting glass matrix. Results from recent full-scale treatment operations in Japan are discussed and plans for GeoMelt treatment of UK nuclear site decommissioning-related asbestos wastes are outlined. (authors)

  15. Activated sludge process: Waste treatment. (Latest citations from the Biobusiness database). Published Search

    SciTech Connect (OSTI)

    Not Available

    1993-10-01

    The bibliography contains citations concerning the use of the activated sludge process in waste and wastewater treatment. Topics include biochemistry of the activated sludge process, effects of various pollutants on process activity, effects of environmental variables such as oxygen and water levels, and nutrient requirements of microorganisms employed in activated sludge processes. The citations also explore use of the process to treat specific wastes, such as halocarbons, metallic wastes, and petrochemical effluents; and wastes from pharmaceutical and dairy processes. (Contains 250 citations and includes a subject term index and title list.)

  16. Activated sludge process: Waste treatment. (Latest citations from the Biobusiness database). Published Search

    SciTech Connect (OSTI)

    Not Available

    1993-07-01

    The bibliography contains citations concerning the use of the activated sludge process in waste and wastewater treatment. Topics include biochemistry of the activated sludge process, effects of various pollutants on process activity, effects of environmental variables such as oxygen and water levels, and nutrient requirements of microorganisms employed in activated sludge processes. The citations also explore use of the process to treat specific wastes, such as halocarbons, metallic wastes, and petrochemical effluents; and wastes from pharmaceutical and dairy processes. (Contains 250 citations and includes a subject term index and title list.)

  17. Activated-sludge process: Waste treatment. (Latest citations from the biobusiness database). Published Search

    SciTech Connect (OSTI)

    Not Available

    1992-07-01

    The bibliography contains citations concerning the use of the activated sludge process in waste and wastewater treatment. Topics include biochemistry of the activated sludge process, effects of various pollutants on process activity, effects of environmental variables such as oxygen and water levels, and nutrient requirements of microorganisms employed in activated sludge processes. The citations also explore use of the process to treat specific wastes, such as halocarbons, metallic wastes, and petrochemical effluents; and wastes from pharmaceutical and dairy processes. (Contains 250 citations and includes a subject term index and title list.)

  18. Summary - Savannah River Site Tank 48H Waste Treatment Project

    Office of Environmental Management (EM)

    and t ess Level (TRL) on Process: stem (TRL3) atment System RA reports, please v govPagesExternal nology Readiness A ng a systematic, me er SiteSRS H Waste Treatm nt of...

  19. Enterprise Assessments Review of the Hanford Site Waste Treatment...

    Energy Savers [EERE]

    by ORP. The mission of the WTP is to process and immobilize the Hanford high-level tank waste into a stable glass form suitable for permanent 2 disposal. The LAW facility is...

  20. 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.; Saunders, Scott A.

    2013-07-01

    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)

  1. Nuclear Waste Treatment Program annual report for FY 1988

    SciTech Connect (OSTI)

    Brouns, R.A.; Powell, J.A.

    1989-11-01

    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.

  2. Review of the Sodium Bearing Waste Treatment Project - Integrated...

    Office of Environmental Management (EM)

    LCO Limiting Condition for Operation LSS Life Safety Systems MSA Management Self-Assessment OFI Opportunity for Improvement ORR Operational Readiness Review OSO Outside Support...

  3. Review of the Sodium Bearing Waste Treatment Project - Integrated...

    Office of Environmental Management (EM)

    canister transfer to the vault). Other evolutions included numerous operational drills, operational activities, simulator operations and scenario proficiency demonstrations,...

  4. Choosing solidification or vitrification for low-level radioactive and mixed waste treatment

    SciTech Connect (OSTI)

    Gimpel, R.F.

    1992-02-14

    Solidification (making concrete) and vitrification (making glass) are frequently the treatment methods recommended for treating inorganic or radioactive wastes. Solidification is generally perceived as the most economical treatment method. Whereas, vitrification is considered (by many) as the most effective of all treatment methods. Unfortunately, vitrification has acquired the stigma that it is too expensive to receive further consideration as an alternative to solidification in high volume treatment applications. Ironically, economic studies, as presented in this paper, show that vitrification may be more competitive in some high volume applications. Ex-situ solidification and vitrification are the competing methods for treating in excess of 450 000m{sup 3} of low-level radioactive and mixed waste at the Fernald Environmental Management Project (FEMP or simply, Fernald) located near Cincinnati, Ohio. This paper summarizes how Fernald is choosing between solidification and vitrification as the primary waste treatment method.

  5. Solid waste integrated cost analysis model: 1991 project year report. Part 2

    SciTech Connect (OSTI)

    Not Available

    1991-12-31

    The purpose of the City of Houston`s 1991 Solid Waste Integrated Cost Analysis Model (SWICAM) project was to continue the development of a computerized cost analysis model. This model is to provide solid waste managers with tool to evaluate the dollar cost of real or hypothetical solid waste management choices. Those choices have become complicated by the implementation of Subtitle D of the Resources Conservation and Recovery Act (RCRA) and the EPA`s Integrated Approach to managing municipal solid waste;. that is, minimize generation, maximize recycling, reduce volume (incinerate), and then bury (landfill) only the remainder. Implementation of an integrated solid waste management system involving all or some of the options of recycling, waste to energy, composting, and landfilling is extremely complicated. Factors such as hauling distances, markets, and prices for recyclable, costs and benefits of transfer stations, and material recovery facilities must all be considered. A jurisdiction must determine the cost impacts of implementing a number of various possibilities for managing, handling, processing, and disposing of waste. SWICAM employs a single Lotus 123 spreadsheet to enable a jurisdiction to predict or assess the costs of its waste management system. It allows the user to select his own process flow for waste material and to manipulate the model to include as few or as many options as he or she chooses. The model will calculate the estimated cost for those choices selected. The user can then change the model to include or exclude waste stream components, until the mix of choices suits the user. Graphs can be produced as a visual communication aid in presenting the results of the cost analysis. SWICAM also allows future cost projections to be made.

  6. SEISMIC DESIGN REQUIREMENTS SELECTION METHODOLOGY FOR THE SLUDGE TREATMENT & M-91 SOLID WASTE PROCESSING FACILITIES PROJECTS

    SciTech Connect (OSTI)

    RYAN GW

    2008-04-25

    In complying with direction from the U.S. Department of Energy (DOE), Richland Operations Office (RL) (07-KBC-0055, 'Direction Associated with Implementation of DOE-STD-1189 for the Sludge Treatment Project,' and 08-SED-0063, 'RL Action on the Safety Design Strategy (SDS) for Obtaining Additional Solid Waste Processing Capabilities (M-91 Project) and Use of Draft DOE-STD-I 189-YR'), it has been determined that the seismic design requirements currently in the Project Hanford Management Contract (PHMC) will be modified by DOE-STD-1189, Integration of Safety into the Design Process (March 2007 draft), for these two key PHMC projects. Seismic design requirements for other PHMC facilities and projects will remain unchanged. Considering the current early Critical Decision (CD) phases of both the Sludge Treatment Project (STP) and the Solid Waste Processing Facilities (M-91) Project and a strong intent to avoid potentially costly re-work of both engineering and nuclear safety analyses, this document describes how Fluor Hanford, Inc. (FH) will maintain compliance with the PHMC by considering both the current seismic standards referenced by DOE 0 420.1 B, Facility Safety, and draft DOE-STD-1189 (i.e., ASCE/SEI 43-05, Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities, and ANSI!ANS 2.26-2004, Categorization of Nuclear Facility Structures, Systems and Components for Seismic Design, as modified by draft DOE-STD-1189) to choose the criteria that will result in the most conservative seismic design categorization and engineering design. Following the process described in this document will result in a conservative seismic design categorization and design products. This approach is expected to resolve discrepancies between the existing and new requirements and reduce the risk that project designs and analyses will require revision when the draft DOE-STD-1189 is finalized.

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

    SciTech Connect (OSTI)

    Torres, T.

    1990-10-01

    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.

  8. Use of chemical precipitation processes in practice of liquid radioactive waste treatment

    SciTech Connect (OSTI)

    Zabrodsky, V.N.; Prokshin, N.E.; Efremenkov, V.M.; Shunkevich, A.A.

    1995-12-31

    In this work information is presented on the installation which is being developed for treatment of liquid radioactive waste. The characteristics of liquid waste generated during decontamination of industrial facilities in Republic of Belarus are also presented. The results of treatment of simulated liquid waste for {sup 137}Cs removal using the method of chemical coprecipitation at different ratios of sedimenting reagents are described. The received data are juxtaposed with the results of sedimentation kinetics of nickel ferrocyanide at the same conditions. The last-named data were obtained by the methods of optical spectrophotometry and radioactive tracers. Methodology of synthesis and properties of cation-exchange fiber FIBAN K-1 modified by cobalt ferrocyanide is described. This sorbent has high sorption ability towards {sup 137}Cs and may be used at the liquid waste treatment facility.

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

    SciTech Connect (OSTI)

    Not Available

    1993-08-01

    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.

  10. 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...

  11. Integrated data base report - 1994: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    SciTech Connect (OSTI)

    1995-09-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel and commercial and U.S. government-owned radioactive wastes. Except for transuranic wastes, inventories of these materials are reported as of December 31, 1994. Transuranic waste inventories are reported as of December 31, 1993. All spent nuclear fuel and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

  12. 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.

    1995-02-01

    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.

  13. Options Assessment Report: Treatment of Nitrate Salt Waste at Los Alamos National Laboratory

    SciTech Connect (OSTI)

    Robinson, Bruce Alan; Stevens, Patrice Ann

    2015-12-17

    This report documents the methodology used to select a method of treatment for the remediated nitrate salt (RNS) and unremediated nitrate salt (UNS) waste containers at Los Alamos National Laboratory (LANL). The method selected should treat the containerized waste in a manner that renders the waste safe and suitable for transport and final disposal in the Waste Isolation Pilot Plant (WIPP) repository, under specifications listed in the WIPP Waste Acceptance Criteria (DOE/CBFO, 2013). LANL recognizes that the results must be thoroughly vetted with the New Mexico Environment Department (NMED) and that a modification to the LANL Hazardous Waste Facility Permit is a necessary step before implementation of this or any treatment option. Likewise, facility readiness and safety basis approvals must be received from the Department of Energy (DOE). This report presents LANL’s preferred option, and the documentation of the process for reaching the recommended treatment option for RNS and UNS waste, and is presented for consideration by NMED and DOE.

  14. Remediation of DOE hazardous waste sites: Planning and integration requirements

    SciTech Connect (OSTI)

    Geffen, C.A.; Garrett, B.A.; Cowan, C.E.; Siegel, M.R.; Keller, J.F. )

    1989-09-01

    The US Department of Energy (DOE) is faced with a immense challenge in effectively implementing a program to mitigate and manage the environmental impacts created by current operations and from past activities at its facilities. The current regulatory framework and public interest in the environmental arena have made operating DOE facilities in an environmentally responsible manner a compelling priority. This paper provides information on the results of a project funded by DOE to obtain a better understanding of the regulatory and institutional drivers in the hazardous waste market and the costs and timeframes required for remediation activities. Few realize that before remediating a hazardous waste site, a comprehensive planning process must be conducted to characterize the nature and extent of site contamination, calculate the risk to the public, and assess the effectiveness of various remediation technologies. The US Environmental Protection Agency (EPA) and others have found that it may take up to 7 years to complete the planning process at an average cost of $1.0 million per site. While cost information is not yet available for DOE sites, discussions with hazardous waste consulting firms indicate that average characterization and assessment costs will be 5 to 10 times this amount for DOE sites. The higher costs are expected because of the additional administrative requirements placed on DOE sites, the need to handle mixed wastes, the amount and extent of contamination at many of these sites, and the visibility of the sites. 15 refs., 1 fig., 2 tabs.

  15. Waste treatment by reverse osmosis and membrane processing. (Latest citations from the NTIS bibliographic database). Published Search

    SciTech Connect (OSTI)

    NONE

    1995-09-01

    The bibliography contains citations concerning the technology of reverse osmosis and membrane processing in sewage and industrial waste treatment. Citations discuss ultrafiltration, industrial water reuse, hazardous waste treatment, municipal wastes, and materials recovery. Waste reduction and recycling in electroplating, metal finishing, and circuit board manufacturing are considered. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

  16. Waste treatment by reverse osmosis and membrane processing. (Latest citations from the NTIS bibliographic database). Published Search

    SciTech Connect (OSTI)

    NONE

    1996-10-01

    The bibliography contains citations concerning the technology of reverse osmosis and membrane processing in sewage and industrial waste treatment. Citations discuss ultrafiltration, industrial water reuse, hazardous waste treatment, municipal wastes, and materials recovery. Waste reduction and recycling in electroplating, metal finishing, and circuit board manufacturing are considered. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

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

    SciTech Connect (OSTI)

    Van Hoesen, S.D.

    2003-09-09

    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.

  18. INITIAL SELECTION OF SUPPLEMENTAL TREATMENT TECHNOLOGIES FOR HANFORDS LOW ACTIVITY TANK WASTE

    SciTech Connect (OSTI)

    RAYMOND, R.E.

    2004-02-20

    In 2002, the U.S. Department of Energy (DOE) documented 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 specific technologies to be evaluated for supplemental treatment of as much as 70% of the low-activity waste (LAW). In concert with this acceleration plan, DOE, the U.S. Environmental Protection Agency, and the Washington State Department of Ecology proposed to accelerate--from 2014 to 2006--the Hanford Federal Facility Agreement and Consent Order milestone (M-62-11) associated with a final decision on the balance of tank waste that is beyond the capacity of the WTP. The DOE Office of River Protection tank farm contractor, CH2M HILL Hanford Group, Inc. (CH2M HILL), was tasked with testing and evaluating selected supplemental technologies to support final decisions on tank waste treatment. Three technologies and corresponding vendors were selected to support an initial technology selection in 2003. The three technologies were containerized grout called cast stone (Fluor Federal Services); bulk vitrification (AMEC Earth and Environmental, Inc.); and steam reforming (THOR Treatment Technologies, LLC.). The cast stone process applies an effective grout waste formulation to the LAW and places the cement-based product in a large container for solidification and disposal. Unlike the WTP LAW treatment, which applies vitrification within continuous-fed joule-heated ceramic melters, bulk vitrification produces a glass waste form using batch melting within the disposal container. Steam reforming produces a granular denitrified mineral waste form using a high-temperature fluidized bed process. An initial supplemental technology selection was completed in December 2003, enabling DOE and CH2M HILL to focus investments in 2004 on the testing and production-scale demonstrations needed to support the 2006 milestone.

  19. Integrity assessment plan for PNL 300 area radioactive hazardous waste tank system. Final report

    SciTech Connect (OSTI)

    NONE

    1996-03-01

    The Pacific Northwest Laboratory (PNL), operated by Battelle Memorial Institute under contract to the U.S. Department of Energy, operates tank systems for the U.S. Department of Energy, Richland Operations Office (DOE-RL), that contain dangerous waste constituents as defined by Washington State Department of Ecology (WDOE) Dangerous Waste Regulations, Washington Administrative Code (WAC) 173-303-040(18). Chapter 173-303-640(2) of the WAC requires the performance of integrity assessments for each existing tank system that treats or stores dangerous waste, except those operating under interim status with compliant secondary containment. This Integrity Assessment Plan (IAP) identifies all tasks that will be performed during the integrity assessment of the PNL-operated Radioactive Liquid Waste Systems (RLWS) associated with the 324 and 325 Buildings located in the 300 Area of the Hanford Site. It describes the inspections, tests, and analyses required to assess the integrity of the PNL RLWS (tanks, ancillary equipment, and secondary containment) and provides sufficient information for adequate budgeting and control of the assessment program. It also provides necessary information to permit the Independent, Qualified, Registered Professional Engineer (IQRPE) to approve the integrity assessment program.

  20. RCRA information on hazardous wastes for publicly owned treatment works. Technical report

    SciTech Connect (OSTI)

    Not Available

    1985-09-01

    The guidance manual provides guidance to municipal personnel in understanding hazardous waste requirements of the Resource Conservation and Recovery Act (RCRA) and the implications of these RCRA requirements for the wastewater treatment plant operated by your municipality, for your local pretreatment program, and for local industries served by the treatment plant. The primary purpose of the manual is the RCRA notification requirement specified in the General Pretreatment Regulations. The manual focuses on Subtitle C requirements. (Subtitle C is directly applicable to industries since this program regulates generators, transporters, and disposers of hazardous waste). The manual also provides a general understanding of how federal RCRA requirements for hazardous waste affect industrial users. The manual also will be helpful in complying with any applicable federal requirements incumbent upon your POTW under Subtitle C of RCRA. The appendices contain lists of hazardous wastes regulated by federal requirements; selected EPA-approved forms for hazardous waste facilities to use; RCRA information brochure which briefly outlines the Act's impact on industries that generate or transport hazardous wastes; and EPA pamphlets summarizing information for generators of small quantities of hazardous waste.

  1. Enterprise Assessments Review of the 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 on Delicious Rank EERE:FinancingPetroleum12, 2015 Infographiclighbulbs -Immobilization Plant Low-Activity Waste

  2. Hanford Tank Waste Retrieval, Treatment, and Disposition Framework |

    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 on Delicious Rank EERE:FinancingPetroleum12,ExecutiveFinancing ProgramsDepartment of Energy Hanford Tank Waste

  3. 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.

    2013-07-01

    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)

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

    SciTech Connect (OSTI)

    Not Available

    1994-06-01

    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.

  5. The Treatment of Mixed Waste with GeoMelt In-Container Vitrification

    SciTech Connect (OSTI)

    Finucane, K.G.; Campbell, B.E.

    2006-07-01

    AMEC's GeoMelt{sup R} In-Container Vitrification (ICV){sup TM} has been used to treat diverse types of mixed low-level radioactive waste. ICV is effective in the treatment of mixed wastes containing polychlorinated biphenyls (PCBs) and other semi-volatile organic compounds, volatile organic compounds (VOCs) and heavy metals. The GeoMelt vitrification process destroys organic compounds and immobilizes metals and radionuclides in an extremely durable glass waste form. The process is flexible allowing for treatment of aqueous, oily, and solid mixed waste, including contaminated soil. In 2004, ICV was used to treat mixed radioactive waste sludge containing PCBs generated from a commercial cleanup project regulated by the Toxic Substances Control Act (TSCA), and to treat contaminated soil from Rocky Flats Environmental Technology Site. The Rocky Flats soil contained cadmium, PCBs, and depleted uranium. In 2005, AMEC completed a treatability demonstration of the ICV technology on Mock High Explosive from Sandia National Laboratories. This paper summarizes results from these mixed waste treatment projects. (authors)

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

    SciTech Connect (OSTI)

    1993-06-01

    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.

  7. 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)

    2013-11-15

    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.

  8. Radioactive waste management integrated data base: a bibliography. [Approximately 1100 references

    SciTech Connect (OSTI)

    Johnson, C.A.; Garland, P.A.

    1980-09-01

    The purpose of this indexed bibliography is to organize and collect the literature references on waste generation and treatment, characteristics, inventories, and costs. The references were captured into a searchable information file, and the information file was sorted, indexed, and printed for this bibliography. A completion of approximately 1100 references to nuclear waste management, the first of a series, is completed. Each reference is categorized by waste origin (commercial, defense, institutional, and foreign) and by subject area: (1) high-level wastes, (2) low-level wastes, (3) TRU wastes, (4) airborne wastes, (5) remedial action (formerly utilized sites, surplus facilities, and mill tailings), (6) isolation, (7) transportation, (8) spent fuel, (9) fuel cycle centers, and (10) a general category that covers nonspecific wastes. Five indexes are provided to assist the user in locating documents of interest: author, author affiliation (corporate authority), subject category, keyword, and permuted title. Machine (computer) searches of these indexes can be made specifying multiple constraints if so desired. This bibliography will be periodically updated as new information becomes available. In addition to being used in searches for specific data, the information file can also be used for resource document collection, names and addresses of contacts, and identification of potential sources of data.

  9. High Level Waste Remote Handling Equipment in the Melter Cave Support Handling System at the Hanford Waste Treatment Plant

    SciTech Connect (OSTI)

    Bardal, M.A. [PaR Systems, Inc., Shoreview, MN (United States); Darwen, N.J. [Bechtel National, Inc., Richland, WA (United States)

    2008-07-01

    Cold war plutonium production led to extensive amounts of radioactive waste stored in tanks at the Department of Energy's (DOE) Hanford site. Bechtel National, Inc. is building the largest nuclear Waste Treatment Plant in the world located at the Department of Energy's Hanford site to immobilize the millions of gallons of radioactive waste. The site comprises five main facilities; Pretreatment, High Level Waste vitrification, Low Active Waste vitrification, an Analytical Lab and the Balance of Facilities. The pretreatment facilities will separate the high and low level waste. The high level waste will then proceed to the HLW facility for vitrification. Vitrification is a process of utilizing a melter to mix molten glass with radioactive waste to form a stable product for storage. The melter cave is designated as the High Level Waste Melter Cave Support Handling System (HSH). There are several key processes that occur in the HSH cell that are necessary for vitrification and include: feed preparation, mixing, pouring, cooling and all maintenance and repair of the process equipment. Due to the cell's high level radiation, remote handling equipment provided by PaR Systems, Inc. is required to install and remove all equipment in the HSH cell. The remote handling crane is composed of a bridge and trolley. The trolley supports a telescoping tube set that rigidly deploys a TR 4350 manipulator arm with seven degrees of freedom. A rotating, extending, and retracting slewing hoist is mounted to the bottom of the trolley and is centered about the telescoping tube set. Both the manipulator and slewer are unique to this cell. The slewer can reach into corners and the manipulator's cross pivoting wrist provides better operational dexterity and camera viewing angles at the end of the arm. Since the crane functions will be operated remotely, the entire cell and crane have been modeled with 3-D software. Model simulations have been used to confirm operational and maintenance functional and timing studies throughout the design process. Since no humans can go in or out of the cell, there are several recovery options that have been designed into the system including jack-down wheels for the bridge and trolley, recovery drums for the manipulator hoist, and a wire rope cable cutter for the slewer jib hoist. If the entire crane fails in cell, the large diameter cable reel that provides power, signal, and control to the crane can be used to retrieve the crane from the cell into the crane maintenance area. (authors)

  10. Waste treatment facility passes federal inspection, completes final

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust,Field-effectWorking WithTelecentricN A 035(92/02)Management Waste Managementmilestone,

  11. Waste Treatment and Immobilation Plant Pretreatment Facility | Department

    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 on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX E LIST OFAMERICA'S FUTURE. regulators consumerWaste Isolationof Energy Pretreatment

  12. Waste Treatment and Immobilization Plant (WTP) Analytical Laboratory (LAB),

    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 on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX E LIST OFAMERICA'S FUTURE. regulators consumerWaste Isolationof Energy

  13. Waste Treatment Facility Saves Taxpayers Nearly $20 Million | Department of

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirley Ann Jackson About1996HowFOAShowingFuel EfficiencyWashington , DC 20585 AprilWasteEnergy

  14. Structural integrity and potential failure modes of hanford high-level waste tanks

    SciTech Connect (OSTI)

    Han, F.C.

    1996-09-30

    Structural Integrity of the Hanford High-Level Waste Tanks were evaluated based on the existing Design and Analysis Documents. All tank structures were found adequate for the normal operating and seismic loads. Potential failure modes of the tanks were assessed by engineering interpretation and extrapolation of the existing engineering documents.

  15. Buried waste integrated demonstration human engineered control station. Final report

    SciTech Connect (OSTI)

    Not Available

    1994-09-01

    This document describes the Human Engineered Control Station (HECS) project activities including the conceptual designs. The purpose of the HECS is to enhance the effectiveness and efficiency of remote retrieval by providing an integrated remote control station. The HECS integrates human capabilities, limitations, and expectations into the design to reduce the potential for human error, provides an easy system to learn and operate, provides an increased productivity, and reduces the ultimate investment in training. The overall HECS consists of the technology interface stations, supporting engineering aids, platform (trailer), communications network (broadband system), and collision avoidance system.

  16. High-tech waste treatment plant to open in Ho Chi Min City (20-07-2005)

    E-Print Network [OSTI]

    Columbia University

    High-tech waste treatment plant to open in Ho Chi Min City (20-07-2005) by Pham Hoang Nam HCM City will recycle waste products into either high quality, low-sulphur synthetic coal or synthetic "scrubbed gas". Pyrolysis, a thermal process that uses high temperatures to break down any waste containing carbon, uses

  17. Conceptual Evaluation for the Installation of Treatment Capability for Mixed Low Level Waste at the Nevada National Security Site

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2010-11-24

    National Security Technologies, LLC, initiated an evaluation of treatment technologies that they would manage and operate as part of the mixed low-level waste (MLLW) disposal facilities at the Nevada National Security Site (NNSS). The NNSS Disposal Facility has been receiving radioactive waste from the U.S. Department of Energy (DOE) complex since the 1960s, and since 2005 the NNSS Disposal Facility has been receiving radioactive and MLLW for disposal only. In accordance with the Resource Conservation and Recovery Act (RCRA), all mixed waste must meet land disposal restrictions (LDRs) prior to disposal. Compliance with LDRs is attained through treatment of the waste to mitigate the characteristics of the listed waste hazard. Presently, most generators utilize commercial capacity for waste treatment prior to shipment to the NNSS Disposal Facility. The objectives of this evaluation are to provide a conceptual study of waste treatment needs (i.e., demand), identify potential waste treatment technologies to meet demand, and analyze implementation considerations for initiating MLLW treatment capacity at the NNSS Disposal Facility. A review of DOE complex waste generation forecast data indicates that current and future Departmental demand for mixed waste treatment capacity will remain steady and strong. Analysis and screening of over 30 treatment technologies narrowed the field of treatment technologies to four: • Macroencapsulation • Stabilization/microencapsulation • Sort and segregation • Bench-scale mercury amalgamation The analysis of treatment technologies also considered existing permits, current the NNSS Disposal Facility infrastructure such as utilities and procedures, and past experiences such as green-light and red-light lessons learned. A schedule duration estimate has been developed for permitting, design, and construction of onsite treatment capability at the NNSS Disposal Facility. Treatment capability can be ready in 20 months.

  18. Advances in the Glass Formulations for the Hanford Tank Waste Treatment and Immobilization Plant

    SciTech Connect (OSTI)

    Kruger, Albert A.; Vienna, John D.; Kim, Dong Sang

    2015-01-14

    The Department of Energy-Office of River Protection (DOE-ORP) is constructing the Hanford Tank Waste Treatment and Immobilization Plant (WTP) to treat radioactive waste currently stored in underground tanks at the Hanford site in Washington. The WTP that is being designed and constructed by a team led by Bechtel National, Inc. (BNI) will separate the tank waste into High Level Waste (HLW) and Low Activity Waste (LAW) fractions with the majority of the mass (~90%) directed to LAW and most of the activity (>95%) directed to HLW. The pretreatment process, envisioned in the baseline, involves the dissolution of aluminum-bearing solids so as to allow the aluminum salts to be processed through the cesium ion exchange and report to the LAW Facility. There is an oxidative leaching process to affect a similar outcome for chromium-bearing wastes. Both of these unit operations were advanced to accommodate shortcomings in glass formulation for HLW inventories. A by-product of this are a series of technical challenges placed upon materials selected for the processing vessels. The advances in glass formulation play a role in revisiting the flow sheet for the WTP and hence, the unit operations that were being imposed by minimal waste loading requirements set forth in the contract for the design and construction of the plant. Another significant consideration to the most recent revision of the glass models are the impacts on resolution of technical questions associated with current efforts for design completion.

  19. US DOE Initiated Performance Enhancements to the Hanford Waste Treatment and Immobilization Plant (WTP) Low-activity Waste Vitrification (LAW) System

    SciTech Connect (OSTI)

    Hamel, William F.; Gerdes, Kurt D.; Holton, Langdon K.; Pegg, Ian L.; Bowen, Brad W.

    2006-03-03

    The U.S Department of Energy Office of River Protection (DOE-ORP) is constructing a Waste Treatment and Immobilization Plant (WTP) for the treatment and vitrification of underground tank wastes stored at the Hanford Site in Washington State. The WTP comprises four major facilities: a pretreatment facility to separate the tank waste into high level waste (HLW) and low-activity waste (LAW) process streams, a HLW vitrification facility to immobilize the HLW fraction; a LAW vitrification facility to immobilize the LAW fraction, and an analytical laboratory to support the operations of all four treatment facilities. DOE has established strategic objectives to optimize the performance of the WTP facilities and the LAW and HLW waste forms to reduce the overall schedule and cost for treatment and vitrification of the Hanford tank wastes. This strategy has been implemented by establishing performance expectations in the WTP contract for the facilities and waste forms. In addition, DOE, as owner-operator of the WTP facilities, continues to evaluate 1) the design, to determine the potential for performance above the requirements specified in the WTP contract; and 2) improvements in production of the LAW and HLW waste forms. This paper reports recent progress directed at improving production of the LAW waste form. DOE’s initial assessment, which is based on the work reported in this paper, is that the capacity of the WTP LAW vitrification facility can be increased by a factor of 2 to 4 with a combination of revised glass formulations, modest increases in melter glass operating temperatures, and a second-generation LAW melter with a larger surface area. Implementing these improvements in the LAW waste immobilization capability can benefit the LAW treatment mission by reducing both processing time and cost.

  20. Volatilization of selected organic compounds from a creosote-waste land-treatment facility. Master's thesis

    SciTech Connect (OSTI)

    Scott, E.J.

    1989-01-01

    The purpose of this research was to evaluate the emissions of volatile and semi-volatile compounds which are constituents of a complex creosote waste from laboratory simulations of a land treatment system to assess the potential human exposure to hazardous compounds from this source. In addition, the Thibodeaux-Hwang Air Emission Release Rate (AERR) model was evaluated for its use in predicting emission rates of hazardous constituents of creosote wood preservative waste from land treatment facilities. A group of hazardous volatile and semi-volatile constituents present in the creosote waste was selected for evaluation in this study and included a variety of polynuclear aromatic hydrocarbons (PNA's), phenol, and chlorinated and substituted phenols.

  1. Integration of the informal sector into municipal solid waste management in the Philippines - What does it need?

    SciTech Connect (OSTI)

    Paul, Johannes G.

    2012-11-15

    The integration of the informal sector into municipal solid waste management is a challenge many developing countries face. In Iloilo City, Philippines around 220 tons of municipal solid waste are collected every day and disposed at a 10 ha large dumpsite. In order to improve the local waste management system the Local Government decided to develop a new Waste Management Center with integrated landfill. However, the proposed area is adjacent to the presently used dumpsite where more than 300 waste pickers dwell and depend on waste picking as their source of livelihood. The Local Government recognized the hidden threat imposed by the waste picker's presence for this development project and proposed various measures to integrate the informal sector into the municipal solid waste management (MSWM) program. As a key intervention a Waste Workers Association, called USWAG Calahunan Livelihood Association Inc. (UCLA) was initiated and registered as a formal business enterprise in May 2009. Up to date, UCLA counts 240 members who commit to follow certain rules and to work within a team that jointly recovers wasted materials. As a cooperative they are empowered to explore new livelihood options such as the recovery of Alternative Fuels for commercial (cement industry) and household use, production of compost and making of handicrafts out of used packages. These activities do not only provide alternative livelihood for them but also lessen the generation of leachate and Greenhouse Gases (GHG) emissions from waste disposal, whereby the life time of the proposed new sanitary landfill can be extended likewise.

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

    E-Print Network [OSTI]

    Angenent, Lars T.

    Interaction between temperature and ammonia in mesophilic digesters for animal waste treatment February 2009 Accepted 20 February 2009 Published online 6 March 2009 Keywords: Ammonia Anaerobic digesters­378), the methane yield was 0.31 L CH4/g volatile solids (VS) for all digesters (with no statistical differences

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

    DOE Patents [OSTI]

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

    2000-01-01

    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.

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

    E-Print Network [OSTI]

    = mg/s #12;Microbial Fuel Cell technology Zielke 1 1 Introduction Renewable energy is an increasing need in our society. Microbial fuel cell (MFC) technology represents a new form of renewable energyApplication of Microbial Fuel Cell technology for a Waste Water Treatment Alternative Eric A

  5. Environmental Assessment Offsite Thermal Treatment of Low-Level Mixed Waste

    SciTech Connect (OSTI)

    N /A

    1999-05-06

    The U.S. Department of Energy (DOE), Richland Operations Office (RL) needs to demonstrate the economics and feasibility of offsite commercial treatment of contact-handled low-level mixed waste (LLMW), containing polychlorinated biphenyls (PCBS) and other organics, to meet existing regulatory standards for eventual disposal.

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

    SciTech Connect (OSTI)

    MINWALL HJ

    2011-04-08

    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.

  7. Borehole Summary Report for Core Hole C4998 – Waste Treatment Plant Seismic Boreholes Project

    SciTech Connect (OSTI)

    Barnett, D. BRENT; Garcia, Benjamin J.

    2006-12-15

    Seismic borehole C4998 was cored through the upper portion of the Columbia River Basalt Group and Ellensburg Formation to provide detailed lithologic information and intact rock samples that represent the geology at the Waste Treatment Plant. This report describes the drilling of borehole C4998 and documents the geologic data collected during the drilling of the cored portion of the borehole.

  8. 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

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

    SciTech Connect (OSTI)

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

    2011-07-21

    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.

  10. Integrated data base report--1996: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    SciTech Connect (OSTI)

    1997-12-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and commercial and U.S. government-owned radioactive wastes. Inventories of most of these materials are reported as of the end of fiscal year (FY) 1996, which is September 30, 1996. Commercial SNF and commercial uranium mill tailings inventories are reported on an end-of-calendar year (CY) basis. All SNF and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are SNF, high-level waste, transuranic waste, low-level waste, uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, naturally occurring and accelerator-produced radioactive material, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through FY 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

  11. The newest achievements of studies on the reutilization, treatment, and disposal technology of hazardous wastes

    SciTech Connect (OSTI)

    Liu Peizhe [Chinese Research Academy of Environmental Sciences, Beijing (China)

    1996-12-31

    From 1991 to 1996, key studies on the reutilization, treatment, and disposal technology of hazardous wastes have been incorporated into the national plan for environmental protection science and technology. At present, the research achievements have been accomplished, have passed national approval, and have been accepted. The author of this paper, as leader of the national group for this research work, expounds the newest achievements of the studies involving four parts: (1) the reutilization technology of electroplating sludge, including the ion-exchange process for recovering the sludge and waste liquor for producing chromium tanning agent and extracting chromium and colloidal protein from tanning waste residue; on the recovery of heavy metals from the electroplating waste liquor with microbic purification; on the demonstration project of producing modified plastics from the sludge and the waste plastics; and on the demonstration of the recovery of heavy metals from waste electroplating sludge by using the ammonia-leaching process; (2) the demonstrative research of reutilization technology of chromium waste residues, including production of self-melting ore and smelting of chromium-containing pig iron, and of pyrolytic detoxification of the residue with cyclone furnace; (3) the incineration technology of hazardous wastes with successful results of the industrial incinerator system for polychlorinated biphenyls; and (4) the safety landfill technology for disposal of hazardous wastes, with a complete set of technology for pretreatment, selection of the site, development of the antipercolating materials, and design and construction of the landfill. Only a part of the achievements is introduced in this paper, most of which has been built and is being operated for demonstration to further spreading application and accumulate experience. 6 refs., 7 figs., 6 tabs.

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

    SciTech Connect (OSTI)

    Not Available

    1993-08-01

    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.

  13. 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.

    2014-09-29

    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.

  14. Setting and stiffening of cementitious components in Cast Stone waste form for disposal of secondary wastes from the Hanford waste treatment and immobilization plant

    SciTech Connect (OSTI)

    Chung, Chul-Woo; Chun, Jaehun, E-mail: jaehun.chun@pnnl.gov; Um, Wooyong; Sundaram, S.K.; Westsik, Joseph H.

    2013-04-01

    Cast Stone is a cementitious waste form, a viable option to immobilize secondary nuclear liquid wastes generated from the Hanford Waste Treatment and Immobilization Plant. However, no study has been performed to understand the flow and stiffening behavior, which is essential to ensure proper workability and is important to safety in a nuclear waste field-scale application. X-ray diffraction, rheology, and ultrasonic wave reflection methods were used to understand the specific phase formation and stiffening of Cast Stone. Our results showed a good correlation between rheological properties of the fresh mixture and phase formation in Cast Stone. Secondary gypsum formation was observed with low concentration simulants, and the formation of gypsum was suppressed in high concentration simulants. A threshold concentration for the drastic change in stiffening was found at 1.56 M Na concentration. It was found that the stiffening of Cast Stone was strongly dependent on the concentration of simulant. Highlights: • A combination of XRD, UWR, and rheology gives a better understanding of Cast Stone. • Stiffening of Cast Stone was strongly dependent on the concentration of simulant. • A drastic change in stiffening of Cast Stone was found at 1.56 M Na concentration.

  15. 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.

    2012-01-12

    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.

  16. Analysis of accident sequences and source terms at treatment and storage facilities for waste generated by US Department of Energy waste management operations

    SciTech Connect (OSTI)

    Mueller, C.; Nabelssi, B.; Roglans-Ribas, J.; Folga, S.; Policastro, A.; Freeman, W.; Jackson, R.; Mishima, J.; Turner, S.

    1996-12-01

    This report documents the methodology, computational framework, and results of facility accident analyses performed for the US Department of Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). The accident sequences potentially important to human health risk are specified, their frequencies assessed, and the resultant radiological and chemical source terms evaluated. A personal-computer-based computational framework and database have been developed that provide these results as input to the WM PEIS for the calculation of human health risk impacts. The WM PEIS addresses management of five waste streams in the DOE complex: low-level waste (LLW), hazardous waste (HW), high-level waste (HLW), low-level mixed waste (LLMW), and transuranic waste (TRUW). Currently projected waste generation rates, storage inventories, and treatment process throughputs have been calculated for each of the waste streams. This report summarizes the accident analyses and aggregates the key results for each of the waste streams. Source terms are estimated, and results are presented for each of the major DOE sites and facilities by WM PEIS alternative for each waste stream. Key assumptions in the development of the source terms are identified. The appendices identify the potential atmospheric release of each toxic chemical or radionuclide for each accident scenario studied. They also discuss specific accident analysis data and guidance used or consulted in this report.

  17. 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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservationBio-Inspired SolarAbout /Two0Photos and Videos/01/2012 Page 1 ofTreatment Plant

  18. Supplemental Treatment Technologies Hanford Advisory Board Tank Waste Committee

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust,Field-effectWorking With Livermore National Lab onSupercriticalVehiclesTreatment

  19. 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.; Niemi, Belinda J.; Paik, Ingle K.; Buczek, Jeffrey A.; Lietzow, J.; McCoy, F.; Beranek, F.; Gupta, M.

    2013-11-07

    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.

  20. 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

    1993-04-01

    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.

  1. Secondary Waste Cast Stone Waste Form Qualification Testing Plan

    SciTech Connect (OSTI)

    Westsik, Joseph H.; Serne, R. Jeffrey

    2012-09-26

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). Cast Stone – a cementitious waste form, has been selected for solidification of this secondary waste stream after treatment in the ETF. The secondary-waste Cast Stone waste form must be acceptable for disposal in the IDF. This secondary waste Cast Stone waste form qualification testing plan outlines the testing of the waste form and immobilization process to demonstrate that the Cast Stone waste form can comply with the disposal requirements. Specifications for the secondary-waste Cast Stone waste form have not been established. For this testing plan, Cast Stone specifications are derived from specifications for the immobilized LAW glass in the WTP contract, the waste acceptance criteria for the IDF, and the waste acceptance criteria in the IDF Permit issued by the State of Washington. This testing plan outlines the testing needed to demonstrate that the waste form can comply with these waste form specifications and acceptance criteria. The testing program must also demonstrate that the immobilization process can be controlled to consistently provide an acceptable waste form product. This testing plan also outlines the testing needed to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support performance assessment analyses of the long-term environmental impact of the secondary-waste Cast Stone waste form in the IDF

  2. Portal dosimetry for VMAT using integrated images obtained during treatment

    SciTech Connect (OSTI)

    Bedford, James L. Hanson, Ian M.; Hansen, Vibeke Nordmark

    2014-02-15

    Purpose: Portal dosimetry provides an accurate and convenient means of verifying dose delivered to the patient. A simple method for carrying out portal dosimetry for volumetric modulated arc therapy (VMAT) is described, together with phantom measurements demonstrating the validity of the approach. Methods: Portal images were predicted by projecting dose in the isocentric plane through to the portal image plane, with exponential attenuation and convolution with a double-Gaussian scatter function. Appropriate parameters for the projection were selected by fitting the calculation model to portal images measured on an iViewGT portal imager (Elekta AB, Stockholm, Sweden) for a variety of phantom thicknesses and field sizes. This model was then used to predict the portal image resulting from each control point of a VMAT arc. Finally, all these control point images were summed to predict the overall integrated portal image for the whole arc. The calculated and measured integrated portal images were compared for three lung and three esophagus plans delivered to a thorax phantom, and three prostate plans delivered to a homogeneous phantom, using a gamma index for 3% and 3 mm. A 0.6 cm{sup 3} ionization chamber was used to verify the planned isocentric dose. The sensitivity of this method to errors in monitor units, field shaping, gantry angle, and phantom position was also evaluated by means of computer simulations. Results: The calculation model for portal dose prediction was able to accurately compute the portal images due to simple square fields delivered to solid water phantoms. The integrated images of VMAT treatments delivered to phantoms were also correctly predicted by the method. The proportion of the images with a gamma index of less than unity was 93.7% ± 3.0% (1SD) and the difference between isocenter dose calculated by the planning system and measured by the ionization chamber was 0.8% ± 1.0%. The method was highly sensitive to errors in monitor units and field shape, but less sensitive to errors in gantry angle or phantom position. Conclusions: This method of predicting integrated portal images provides a convenient means of verifying dose delivered using VMAT, with minimal image acquisition and data processing requirements.

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

    SciTech Connect (OSTI)

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

    2011-01-12

    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.

  4. 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.

    1987-09-01

    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.

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

    SciTech Connect (OSTI)

    Arm, Stuart T.; Pell, Michael J.; Van Meighem, Jeffery S.; Duncan, Garth M.; Harrington, Christopher C.

    2012-11-20

    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.

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

    SciTech Connect (OSTI)

    Cimpan, Ciprian Wenzel, Henrik

    2013-07-15

    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.

  7. Environmental assessment for the treatment of Class A low-level radioactive waste and mixed low-level waste generated by the West Valley Demonstration Project

    SciTech Connect (OSTI)

    NONE

    1995-11-01

    The U.S. Department of Energy (DOE) is currently evaluating low-level radioactive waste management alternatives at the West Valley Demonstration Project (WVDP) located on the Western New York Nuclear Service Center (WNYNSC) near West Valley, New York. The WVDP`s mission is to vitrify high-level radioactive waste resulting from commercial fuel reprocessing operations that took place at the WNYNSC from 1966 to 1972. During the process of high-level waste vitrification, low-level radioactive waste (LLW) and mixed low-level waste (MILLW) will result and must be properly managed. It is estimated that the WVDP`s LLW storage facilities will be filled to capacity in 1996. In order to provide sufficient safe storage of LLW until disposal options become available and partially fulfill requirements under the Federal Facilities Compliance Act (FFCA), the DOE is proposing to use U.S. Nuclear Regulatory Commission-licensed and permitted commercial facilities in Oak Ridge, Tennessee; Clive, Utah; and Houston, Texas to treat (volume-reduce) a limited amount of Class A LLW and MLLW generated from the WVDP. Alternatives for ultimate disposal of the West Valley LLW are currently being evaluated in an environmental impact statement. This proposed action is for a limited quantity of waste, over a limited period of time, and for treatment only; this proposal does not include disposal. The proposed action consists of sorting, repacking, and loading waste at the WVDP; transporting the waste for commercial treatment; and returning the residual waste to the WVDP for interim storage. For the purposes of this assessment, environmental impacts were quantified for a five-year operating period (1996 - 2001). Alternatives to the proposed action include no action, construction of additional on-site storage facilities, construction of a treatment facility at the WVDP comparable to commercial treatment, and off-site disposal at a commercial or DOE facility.

  8. Simulation of integrated pollutant removal (IPR) water-treatment system using ASPEN Plus

    SciTech Connect (OSTI)

    Harendra, Sivaram; Oryshcyhn, Danylo [U.S. DOE Ochs, Thomas [U.S. DOE Gerdemann, Stephen; Clark, John

    2013-01-01

    Capturing CO2 from fossil fuel combustion provides an opportunity for tapping a significant water source which can be used as service water for a capture-ready power plant and its peripherals. Researchers at the National Energy Technology Laboratory (NETL) have patented a process—Integrated Pollutant Removal (IPR®)—that uses off-the-shelf technology to produce a sequestration ready CO2 stream from an oxy-combustion power plant. Water condensed from oxy-combustion flue gas via the IPR system has been analyzed for composition and an approach for its treatment—for in-process reuse and for release—has been outlined. A computer simulation model in ASPEN Plus has been developed to simulate water treatment of flue gas derived wastewater from IPR systems. At the field installation, water condensed in the IPR process contains fly ash particles, sodium (largely from spray-tower buffering) and sulfur species as well as heavy metals, cations, and anions. An IPR wastewater treatment system was modeled using unit operations such as equalization, coagulation and flocculation, reverse osmosis, lime softening, crystallization, and pH correction. According to the model results, 70% (by mass) of the inlet stream can be treated as pure water, the other 20% yields as saleable products such as gypsum (CaSO4) and salt (NaCl) and the remaining portion is the waste. More than 99% of fly ash particles are removed in the coagulation and flocculation unit and these solids can be used as filler materials in various applications with further treatment. Results discussed relate to a slipstream IPR installation and are verified experimentally in the coagulation/flocculation step.

  9. 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.

  10. Borehole Gravity Meter Surveys at the Waste Treatment Plant, Hanford, Washington.

    SciTech Connect (OSTI)

    MacQueen, Jeffrey D.; Mann, Ethan

    2007-04-06

    Microg-LaCoste (MGL) was contracted by Pacfic Northwest National Laboratories (PNNL) to record borehole gravity density data in 3 wells at the HanfordWaste Treatment Plant (WTP) site. The survey was designed to provide highly accurate density information for use in seismic modeling. The borehole gravity meter (BHGM) tool has a very large depth of investigation (hundreds of feet) compared to other density tools so it is not influenced by casing or near welbore effects, such as washouts.

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

    SciTech Connect (OSTI)

    GRIFFIN PW

    2009-08-27

    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.

  12. Integrated Facilities Disposition Program

    Office of Environmental Management (EM)

    Hole 8 Plume 6 Managed by UT-Battelle for the U.S. Department of Energy Remediating aging waste treatment and collection systems is an integral part of the Central Campus...

  13. Technetium Incorporation in Glass for the Hanford Tank Waste Treatment and Immobilization Plant

    SciTech Connect (OSTI)

    Kruger, Albert A.; Kim, Dong Sang

    2015-01-14

    A priority of the United States Department of Energy (U.S. DOE) is to dispose of nuclear wastes accumulated in 177 underground tanks at the Hanford Nuclear Reservation in eastern Washington State. These nuclear wastes date from the Manhattan Project of World War II and from plutonium production during the Cold War. The DOE plans to separate high-level radioactive wastes from low activity wastes and to treat each of the waste streams by vitrification (immobilization of the nuclides in glass) for disposal. The immobilized low-activity waste will be disposed of here at Hanford and the immobilized high-level waste at the national geologic repository. Included in the inventory of highly radioactive wastes is large volumes of 99Tc (?9 × 10E2 TBq or ?2.5 × 104 Ci or ?1500 kg). A problem facing safe disposal of Tc-bearing wastes is the processing of waste feed into in a chemically durable waste form. Technetium incorporates poorly into silicate glass in traditional glass melting. It readily evaporates during melting of glass feeds and out of the molten glass, leading to a spectrum of high-to-low retention (ca. 20 to 80%) in the cooled glass product. DOE-ORP currently has a program at Pacific Northwest National Laboratory (PNNL), in the Department of Materials Science and Engineering at Rutgers University and in the School of Mechanical and Materials Engineering at Washington State University that seeks to understand aspects of Tc retention by means of studying Tc partitioning, molten salt formation, volatilization pathways, and cold cap chemistry. Another problem involves the stability of Tc in glass in both the national geologic repository and on-site disposal after it has been immobilized. The major environmental concern with 99Tc is its high mobility in addition to a long half-life (2.1×105 yrs). The pertechnetate ion (TcO4-) is highly soluble in water and does not adsorb well onto the surface of minerals and so migrates nearly at the same velocity as groundwater. Long-term corrosion of glass waste forms is an area of current interest to the DOE, but attention to the release of Tc from glass has been little explored. It is expected that the release of Tc from glass should be highly dependent on the local glass structure as well as the chemistry of the surrounding environment, including groundwater pH. Though the speciation of Tc in glass has been previously studied, and the Tc species present in waste glass have been previously reported, environmental Tc release mechanisms are poorly understood. The recent advances in Tc chemistry that have given rise to an understanding of incorporation in the glass giving rise to significantly higher single-pass retention during vitrification are presented. Additionally, possible changes to the baseline flowsheet that allow for relatively minor volumes of Tc reporting to secondary waste treatment will be discussed.

  14. 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.

    1996-12-01

    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.

  15. Waste Classification based on Waste Form Heat Generation in Advanced Nuclear Fuel Cycles Using the Fuel-Cycle Integration and Tradeoffs (FIT) Model

    SciTech Connect (OSTI)

    Denia Djokic; Steven J. Piet; Layne F. Pincock; Nick R. Soelberg

    2013-02-01

    This study explores the impact of wastes generated from potential future fuel cycles and the issues presented by classifying these under current classification criteria, and discusses the possibility of a comprehensive and consistent characteristics-based classification framework based on new waste streams created from advanced fuel cycles. A static mass flow model, Fuel-Cycle Integration and Tradeoffs (FIT), was used to calculate the composition of waste streams resulting from different nuclear fuel cycle choices. This analysis focuses on the impact of waste form heat load on waste classification practices, although classifying by metrics of radiotoxicity, mass, and volume is also possible. The value of separation of heat-generating fission products and actinides in different fuel cycles is discussed. It was shown that the benefits of reducing the short-term fission-product heat load of waste destined for geologic disposal are neglected under the current source-based radioactive waste classification system , and that it is useful to classify waste streams based on how favorable the impact of interim storage is in increasing repository capacity.

  16. Waste Classification based on Waste Form Heat Generation in Advanced Nuclear Fuel Cycles Using the Fuel-Cycle Integration and Tradeoffs (FIT) Model - 13413

    SciTech Connect (OSTI)

    Djokic, Denia [Department of Nuclear Engineering, University of California - Berkeley, 4149 Etcheverry Hall, Berkeley, CA 94720-1730 (United States)] [Department of Nuclear Engineering, University of California - Berkeley, 4149 Etcheverry Hall, Berkeley, CA 94720-1730 (United States); Piet, Steven J.; Pincock, Layne F.; Soelberg, Nick R. [Idaho National Laboratory - INL, 2525 North Fremont Avenue, Idaho Falls, ID 83415 (United States)] [Idaho National Laboratory - INL, 2525 North Fremont Avenue, Idaho Falls, ID 83415 (United States)

    2013-07-01

    This study explores the impact of wastes generated from potential future fuel cycles and the issues presented by classifying these under current classification criteria, and discusses the possibility of a comprehensive and consistent characteristics-based classification framework based on new waste streams created from advanced fuel cycles. A static mass flow model, Fuel-Cycle Integration and Tradeoffs (FIT), was used to calculate the composition of waste streams resulting from different nuclear fuel cycle choices. This analysis focuses on the impact of waste form heat load on waste classification practices, although classifying by metrics of radiotoxicity, mass, and volume is also possible. The value of separation of heat-generating fission products and actinides in different fuel cycles is discussed. It was shown that the benefits of reducing the short-term fission-product heat load of waste destined for geologic disposal are neglected under the current source-based radioactive waste classification system, and that it is useful to classify waste streams based on how favorable the impact of interim storage is in increasing repository capacity. (authors)

  17. 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.

    2014-01-21

    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

  18. Integration of alternative feedstreams for biomass treatment and utilization

    DOE Patents [OSTI]

    Hennessey, Susan Marie (Avondale, PA); Friend, Julie (Claymont, DE); Dunson, Jr., James B. (Newark, DE); Tucker, III, Melvin P. (Lakewood, CO); Elander, Richard T. (Evergreen, CO); Hames, Bonnie (Westminster, CO)

    2011-03-22

    The present invention provides a method for treating biomass composed of integrated feedstocks to produce fermentable sugars. One aspect of the methods described herein includes a pretreatment step wherein biomass is integrated with an alternative feedstream and the resulting integrated feedstock, at relatively high concentrations, is treated with a low concentration of ammonia relative to the dry weight of biomass. In another aspect, a high solids concentration of pretreated biomass is integrated with an alternative feedstream for saccharifiaction.

  19. The integrated melter off-gas treatment systems at the West Valley Demonstration Project

    SciTech Connect (OSTI)

    Vance, R.F.

    1991-12-01

    The West Valley Demonstration project was established by an act of Congress in 1980 to solidify the high level radioactive liquid wastes produced from operation of the Western New York Nuclear Services Center from 1966 to 1972. The waste will be solidified as borosilicate glass. This report describes the functions, the controlling design criteria, and the resulting design of the melter off-gas treatment systems.

  20. Evaluation of density separation and other treatment methods for plastic media blasting (PMB) waste

    SciTech Connect (OSTI)

    Spence, R.D.; Morgan, I.L.; Trotter, D.R.

    1995-05-01

    The United States Air Force has developed plastic media blasting (PMB) to replace solvent paint stripping of its aircraft. This paint blasting operation generates a waste stream of mainly pulverized plastic, but the stream also contains enough paint pigments to make the PMB waste RCRA hazardous. A Phase I study identified density separation as the preferred treatment alternative to land disposal of the entire PMB waste stream in a hazardous landfill. This study found density separation to be a less attractive alternative to self-encapsulation, solidification/stabilization (S/S), and low-temperature ashing. Self-encapsulation resulted in a volume decrease but only moderate improvement in Toxicity Characteristic Leaching Procedure (TCLP) performance Solidification/Stabilization (S/S) into cementiaous waste for resulted in excellent TCLP performances, but volume increases. Low-temperature ashing resulted in dramatic volume decreases, but off-gas control is required to contain all the RCRA metals. The resulting ash must be stabilized (e.g., S/S) to meet TCLP limits.

  1. 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

    2013-03-01

    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.

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

    SciTech Connect (OSTI)

    1997-01-01

    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.

  3. Reduction of carbon content in waste-tire combustion ashes by bio-thermal treatment

    SciTech Connect (OSTI)

    Chen, C.C.; Lee, W.J.; Shih, S.I.; Mou, J.L.

    2009-07-01

    Application of bio-catalyst (NOE-7F) in thermal treatment can adequately dispose dark-black fly ashes from co-combustion of both waste tires and coal. After thermal treatment of fly ashes by adding 10% NOE-7F, the carbon contents reduced by 37.6% and the weight losses increased by 405%, compared with the fly ashes without mixing with NOE-7F. The combustion behaviors of wasted tires combustion fly ashes with NOE-7F were also investigated by both thermogravimetric analysis (TGA) and differential thermal analysis (DTA). The results verify that NOE-7F has positive effects on the combustion of residual carbon and toxic polycyclic aromatic hydrocarbons (PAHs) enhance the energy release and reduce the toxicity during the process of thermal treatment. Furthermore, using NOE-7F to dispose high-carbon content fly ashes did improve the compressive strength of fly ashes and concrete mixtures. Therefore, NOE-7F is a promising additive which could decrease treatment cost of high-carbon content fly ashes and reduce the amount of survival toxic PAHs.

  4. 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.

    1996-07-01

    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.

  5. 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.

    1994-11-01

    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).

  6. Hanford waste treatment plant Immobilized High Level Waste (IHLW) canister radiation dose rate and radiolytic heat load analysis

    SciTech Connect (OSTI)

    PIERSON, R.M.

    2003-09-02

    This document provides an analysis of anticipated radiation dose rates and heat loads for immobilized high level waste (IHW) canisters

  7. 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

    2009-12-28

    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.

  8. Treatment of contaminated waste-site runoff at the Seymour Recycling Site, Seymour, Indiana

    SciTech Connect (OSTI)

    Traver, R.P.

    1985-01-01

    The Environmental Emergency Response Unit (EERU) is the U.S. Environmental Protection Agency's (EPA) hazardous-material-spill response and control organization for situations where the use of complex cleanup equipment and techniques are required. EERU is engaged in the shakedown and field demonstration of protypical equipment and techniques developed under the direction and sponsorship of EPA's Hazardous Waste Engineering Research Laboratory (HWERL). In March 1983, EERU was requested by the EPA Region V On-Scene-Coordinator to provide an on-site water-treatment system at the Seymour Recycling Site, Seymour, Indiana, the largest uncontrolled waste site in the state. The system was to be on-site and operational by April 1983. A few of the limiting factors in choosing a system were speed of mobilization, plus short-term and intermittent use.

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

    SciTech Connect (OSTI)

    Ragsdale, R.G., Jr

    1994-12-01

    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.

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

    SciTech Connect (OSTI)

    Beeman, Gordon H.

    2010-08-12

    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.

  11. 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.

    2010-03-07

    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.

  12. 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))

    1992-01-01

    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.

  13. Description of recommended non-thermal mixed waste treatment technologies: Version 1.0

    SciTech Connect (OSTI)

    1995-08-01

    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.

  14. Challenge problem and milestones for : Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC).

    SciTech Connect (OSTI)

    Freeze, Geoffrey A.; Wang, Yifeng; Howard, Robert; McNeish, Jerry A.; Schultz, Peter Andrew; Arguello, Jose Guadalupe, Jr.

    2010-09-01

    This report describes the specification of a challenge problem and associated challenge milestones for the Waste Integrated Performance and Safety Codes (IPSC) supporting the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The NEAMS challenge problems are designed to demonstrate proof of concept and progress towards IPSC goals. The goal of the Waste IPSC is to develop an integrated suite of modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. To demonstrate proof of concept and progress towards these goals and requirements, a Waste IPSC challenge problem is specified that includes coupled thermal-hydrologic-chemical-mechanical (THCM) processes that describe (1) the degradation of a borosilicate glass waste form and the corresponding mobilization of radionuclides (i.e., the processes that produce the radionuclide source term), (2) the associated near-field physical and chemical environment for waste emplacement within a salt formation, and (3) radionuclide transport in the near field (i.e., through the engineered components - waste form, waste package, and backfill - and the immediately adjacent salt). The initial details of a set of challenge milestones that collectively comprise the full challenge problem are also specified.

  15. Guidelines for development of structural integrity programs for DOE high-level waste storage tanks

    SciTech Connect (OSTI)

    Bandyopadhyay, K.; Bush, S.; Kassir, M.; Mather, B.; Shewmon, P.; Streicher, M.; Thompson, B.; Rooyen, D. van; Weeks, J.

    1997-01-01

    Guidelines are provided for developing programs to promote the structural integrity of high-level waste storage tanks and transfer lines at the facilities of the Department of Energy. Elements of the program plan include a leak-detection system, definition of appropriate loads, collection of data for possible material and geometric changes, assessment of the tank structure, and non-destructive examination. Possible aging degradation mechanisms are explored for both steel and concrete components of the tanks, and evaluated to screen out nonsignificant aging mechanisms and to indicate methods of controlling the significant aging mechanisms. Specific guidelines for assessing structural adequacy will be provided in companion documents. Site-specific structural integrity programs can be developed drawing on the relevant portions of the material in this document.

  16. GeoMelt{sup R} ICV{sup TM} Treatment of Sellafield Pond Solids Waste - 13414

    SciTech Connect (OSTI)

    Witwer, Keith; Woosley, Steve; Campbell, Brett [Kurion, Inc., GeoMelt Division, 3015 Horn Rapids Road, Richland, Washington (United States)] [Kurion, Inc., GeoMelt Division, 3015 Horn Rapids Road, Richland, Washington (United States); Wong, Martin; Hill, Joanne [AMEC Inc., Birchwood Park, 601 Faraday Street, Birchwood, Warrington, WA3 6GN (United Kingdom)] [AMEC Inc., Birchwood Park, 601 Faraday Street, Birchwood, Warrington, WA3 6GN (United Kingdom)

    2013-07-01

    Kurion, Inc., in partnership with AMEC Ltd., is demonstrating its GeoMelt{sup R} In-Container Vitrification (ICV){sup TM} Technology to Sellafield Ltd. (SL). SL is evaluating the proposition of directly converting a container (skip/box/drum) of raw solid ILW into an immobilized waste form using thermal treatment, such that the resulting product is suitable for interim storage at Sellafield and subsequent disposal at a future Geological Disposal Facility. Potential SL feed streams include sludges, ion-exchange media, sand, plutonium contaminated material, concrete, uranium, fuel cladding, soils, metals, and decommissioning wastes. The solid wastes have significant proportions of metallic constituents in the form of containers, plant equipment, structural material and swarf arising from the nuclear operations at Sellafield. GeoMelt's proprietary ICV process was selected for demonstration, with the focus being high and reactive metal wastes arising from solid ILW material. A composite surrogate recipe was used to demonstrate the technology towards treating waste forms of diverse types and shapes, as well as those considered difficult to process; all the while requiring few (if any) pre-treatment activities. Key strategic objectives, along with their success criterion, were established by SL for this testing, namely: 1. Passivate and stabilize the raw waste simulant, as demonstrated by the entire quantity of material being vitrified, 2. Immobilize the radiological and chemo-toxic species, as demonstrated via indicative mass balance using elemental analyses from an array of samples, 3. Production of an inert and durable product as evidenced by transformation of reactive metals to their inert oxide forms and satisfactory leachability results using PCT testing. Two tests were performed using the GeoMelt Demonstration Unit located at AMEC's Birchwood Park Facilities in the UK. Post-melt examination of the first test indicated some of the waste simulant had not fully processed, due to insufficient processing time and melt temperature. A second test, incorporating operational experience from the first test, was performed and resulted in all of the 138 kg of feed material being treated. The waste simulant portion, at 41 kg, constituted 30 wt% of the total feed mass, with over 90% of this being made up of various reactive and non-reactive metals. The 95 liters of staged material was volume reduced to 41 liters, providing a 57% overall feed to product volume reduction in a fully passivated two-phase glass/metal product. The GeoMelt equipment operated as designed, vitrifying the entire batch of waste simulant. Post-melt analytical testing verified that 91-99+% of the radiological tracer metals were uniformly distributed within the glass/cast refractory/metal product, and the remaining fraction was captured in the offgas filtration systems. PCT testing of the glass and inner refractory liner showed leachability results that outperform the DOE regulatory limit of 2 g/m{sup 2} for the radiological species of interest (Sr, Ru, Cs, Eu, Re), and by more than an order of magnitude better for standard reference analytes (B, Na, Si). (authors)

  17. Integrated Closure and Monitoring Plan for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site

    SciTech Connect (OSTI)

    Bechtel Nevada

    2005-06-01

    This document is an integrated plan for closing and monitoring two low-level radioactive waste disposal sites at the Nevada Test Site.

  18. DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submit theCovalent Bonding Low-Cost Ground8Department ofMixed Waste Treatment

  19. 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

    1999-05-10

    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.

  20. 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; Wiles Elder

    1999-04-05

    This eleventh quarterly report describes work done during the eleventh 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 and giving presentations, and making and responding to two outside contacts.

  1. 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

    1999-06-01

    This sixteenth quarterly report describes work done during the sixteenth 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, giving a presentation, and making and responding to several outside contacts.

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

    SciTech Connect (OSTI)

    Coenenberg, J.G.

    1997-08-15

    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.

  3. Waste Management Information System (WMIS) User Guide

    SciTech Connect (OSTI)

    R. E. Broz

    2008-12-22

    This document provides the user of the Waste Management Information System (WMIS) instructions on how to use the WMIS software. WMIS allows users to initiate, track, and close waste packages. The modular design supports integration and utilization of data throuh the various stages of waste management. The phases of the waste management work process include generation, designation, packaging, container management, procurement, storage, treatment, transportation, and disposal.

  4. TECHNICAL ASSESSMENT OF BULK VITRIFICATION PROCESS & PRODUCT FOR TANK WASTE TREATMENT AT THE DEPARTMENT OF ENERGY HANFORD SITE

    SciTech Connect (OSTI)

    SCHAUS, P.S.

    2006-07-21

    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.

  5. Minimizing Waste from the Oil Industry: Scale Treatment and Scrap Recycling

    SciTech Connect (OSTI)

    Lindberg, M.

    2002-02-26

    Naturally occurring radioactive material is technologically concentrated in the piping in systems in the oil and gas industry, especially in the offshore facilities. The activity, mainly Ra-226, in the scales in the systems are often at levels classified as low level radioactive waste (LSA) in the industry. When the components and pipes are descaled for maintenance or recycling purposes, usually by high-pressure water jetting, the LSA scales arising constitute a significant quantity of radioactive waste for disposal. A new process is under development for the treatment of scales, where the radioactive solids are separated from the inactive. This would result in a much smaller fraction to be deposited as radioactive waste. The radioactive part recovered from the scales will be reduced to a stable non-metallic salt and because the volume is significantly smaller then the original material, will minimize the cost for disposal. The pipes, that have been cleaned by high pressure water jetting can either be reused or free released by scrapping and melting for recycling.

  6. Technical Basis for Certification of Seismic Design Criteria for the Waste Treatment Plant, Hanford, Washington

    SciTech Connect (OSTI)

    Brouns, Thomas M.; Rohay, Alan C.; Youngs, Robert R.; Costantino, Carl J.; Miller, Lewis F.

    2008-02-28

    In August 2007, Secretary of Energy Samuel W. Bodman approved the final seismic and ground motion criteria for the Waste Treatment and Immobilization Plant (WTP) at the Department of Energy’s (DOE) Hanford Site. Construction of the WTP began in 2002 based on seismic design criteria established in 1999 and a probabilistic seismic hazard analysis completed in 1996. The design criteria were re-evaluated in 2005 to address questions from the Defense Nuclear Facilities Safety Board (DNFSB), resulting in an increase by up to 40% in the seismic design basis. DOE announced in 2006 the suspension of construction on the pretreatment and high-level waste vitrification facilities within the WTP to validate the design with more stringent seismic criteria. In 2007, the U.S. Congress mandated that the Secretary of Energy certify the final seismic and ground motion criteria prior to expenditure of funds on construction of these two facilities. With the Secretary’s approval of the final seismic criteria this past summer, DOE authorized restart of construction of the pretreatment and high-level waste vitrification facilities.

  7. Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) verification and validation plan. version 1.

    SciTech Connect (OSTI)

    Bartlett, Roscoe Ainsworth; Arguello, Jose Guadalupe, Jr.; Urbina, Angel; Bouchard, Julie F.; Edwards, Harold Carter; Freeze, Geoffrey A.; Knupp, Patrick Michael; Wang, Yifeng; Schultz, Peter Andrew; Howard, Robert (Oak Ridge National Laboratory, Oak Ridge, TN); McCornack, Marjorie Turner

    2011-01-01

    The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. To meet this objective, NEAMS Waste IPSC M&S capabilities will be applied to challenging spatial domains, temporal domains, multiphysics couplings, and multiscale couplings. A strategic verification and validation (V&V) goal is to establish evidence-based metrics for the level of confidence in M&S codes and capabilities. Because it is economically impractical to apply the maximum V&V rigor to each and every M&S capability, M&S capabilities will be ranked for their impact on the performance assessments of various components of the repository systems. Those M&S capabilities with greater impact will require a greater level of confidence and a correspondingly greater investment in V&V. This report includes five major components: (1) a background summary of the NEAMS Waste IPSC to emphasize M&S challenges; (2) the conceptual foundation for verification, validation, and confidence assessment of NEAMS Waste IPSC M&S capabilities; (3) specifications for the planned verification, validation, and confidence-assessment practices; (4) specifications for the planned evidence information management system; and (5) a path forward for the incremental implementation of this V&V plan.

  8. Application of integrated constructed wetlands for contaminant treatment and diffusion 

    E-Print Network [OSTI]

    Dong, Yu

    2013-07-01

    The sediment accumulation is an important characteristic in the ageing process of integrated constructed wetlands (ICW). Retained nutrient and other contaminants in wetland sediments have the potential to be remobilized ...

  9. Examining the effectiveness of municipal solid waste management systems: An integrated cost-benefit analysis perspective with a financial cost modeling in Taiwan

    SciTech Connect (OSTI)

    Weng, Yu-Chi; Fujiwara, Takeshi

    2011-06-15

    In order to develop a sound material-cycle society, cost-effective municipal solid waste (MSW) management systems are required for the municipalities in the context of the integrated accounting system for MSW management. Firstly, this paper attempts to establish an integrated cost-benefit analysis (CBA) framework for evaluating the effectiveness of MSW management systems. In this paper, detailed cost/benefit items due to waste problems are particularly clarified. The stakeholders of MSW management systems, including the decision-makers of the municipalities and the citizens, are expected to reconsider the waste problems in depth and thus take wise actions with the aid of the proposed CBA framework. Secondly, focusing on the financial cost, this study develops a generalized methodology to evaluate the financial cost-effectiveness of MSW management systems, simultaneously considering the treatment technological levels and policy effects. The impacts of the influencing factors on the annual total and average financial MSW operation and maintenance (O and M) costs are analyzed in the Taiwanese case study with a demonstrative short-term future projection of the financial costs under scenario analysis. The established methodology would contribute to the evaluation of the current policy measures and to the modification of the policy design for the municipalities.

  10. 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)

    2013-07-01

    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)

  11. Solid Waste Integrated Forecast Technical (SWIFT) Report FY2001 to FY2046 Volume 1

    SciTech Connect (OSTI)

    BARCOT, R.A.

    2000-08-31

    This report provides up-to-date life cycle information about the radioactive solid waste expected to be managed by Hanford's Waste Management (WM) Project from onsite and offsite generators. It includes: an overview of Hanford-wide solid waste to be managed by the WM Project; program-level and waste class-specific estimates; background information on waste sources; and comparisons to previous forecasts and other national data sources. This report does not include: waste to be managed by the Environmental Restoration (EM-40) contractor (i.e., waste that will be disposed of at the Environmental Restoration Disposal Facility (ERDF)); waste that has been received by the WM Project to date (i.e., inventory waste); mixed low-level waste that will be processed and disposed by the River Protection Program; and liquid waste (current or future generation). Although this report currently does not include liquid wastes, they may be added as information becomes available.

  12. Development of an Integrated Raman and Turbidity Fiber Optic Sensor for the In-Situ Analysis of High Level Nuclear Waste

    SciTech Connect (OSTI)

    Gasbarro, Christina; Bello, Job M.; Bryan, Samuel A.; Lines, Amanda M.; Levitskaia, Tatiana G.

    2013-02-24

    Stored nuclear waste must be retrieved from storage, treated, separated into low- and high-level waste streams, and finally put into a disposal form that effectively encapsulates the waste and isolates it from the environment for a long period of time. Before waste retrieval can be done, waste composition needs to be characterized so that proper safety precautions can be implemented during the retrieval process. In addition, there is a need for active monitoring of the dynamic chemistry of the waste during storage since the waste composition can become highly corrosive. This work describes the development of a novel, integrated fiber optic Raman and light scattering probe for in situ use in nuclear waste solutions. The dual Raman and turbidity sensor provides simultaneous chemical identification of nuclear waste as well as information concerning the suspended particles in the waste using a common laser excitation source.

  13. Development of an Integrated Raman and Turbidity Fiber Optic Sensor for the In-Situ Analysis of High Level Nuclear Waste - 13532

    SciTech Connect (OSTI)

    Gasbarro, Christina; Bello, Job [EIC Laboratories, Inc., 111 Downey St., Norwood, MA, 02062 (United States)] [EIC Laboratories, Inc., 111 Downey St., Norwood, MA, 02062 (United States); Bryan, Samuel; Lines, Amanda; Levitskaia, Tatiana [Pacific Northwest National Laboratory, PO Box 999, Richland, WA, 99352 (United States)] [Pacific Northwest National Laboratory, PO Box 999, Richland, WA, 99352 (United States)

    2013-07-01

    Stored nuclear waste must be retrieved from storage, treated, separated into low- and high-level waste streams, and finally put into a disposal form that effectively encapsulates the waste and isolates it from the environment for a long period of time. Before waste retrieval can be done, waste composition needs to be characterized so that proper safety precautions can be implemented during the retrieval process. In addition, there is a need for active monitoring of the dynamic chemistry of the waste during storage since the waste composition can become highly corrosive. This work describes the development of a novel, integrated fiber optic Raman and light scattering probe for in situ use in nuclear waste solutions. The dual Raman and turbidity sensor provides simultaneous chemical identification of nuclear waste as well as information concerning the suspended particles in the waste using a common laser excitation source. (authors)

  14. Mixed and Low-Level Waste Treatment Facility project. Appendix A, Environmental and regulatory planning and documentation: Draft

    SciTech Connect (OSTI)

    Not Available

    1992-04-01

    Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report, Appendix A, Environmental & Regulatory Planning & Documentation, identifies the regulatory requirements that would be imposed on the operation or construction of a facility designed to process the INEL`s waste streams. These requirements are contained in five reports that discuss the following topics: (1) an environmental compliance plan and schedule, (2) National Environmental Policy Act requirements, (3) preliminary siting requirements, (4) regulatory justification for the project, and (5) health and safety criteria.

  15. Proposal for the award of a contract for the collection, transport, removal and treatment of conventional waste produced on the CERN sites

    E-Print Network [OSTI]

    2012-01-01

    Proposal for the award of a contract for the collection, transport, removal and treatment of conventional waste produced on the CERN sites

  16. Proposal for the award of a contract for the design, supply, installation, commissioning and maintenance of a compressing and shearing machine for the CERN Radioactive Waste Treatment Centre

    E-Print Network [OSTI]

    2013-01-01

    Proposal for the award of a contract for the design, supply, installation, commissioning and maintenance of a compressing and shearing machine for the CERN Radioactive Waste Treatment Centre

  17. 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

  18. Transuranic 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)

    Hong, K.; Kotek, T.; Folga, S.; Koebnick, B.; Wang, Y.; Kaicher, C.

    1996-12-01

    Transuranic waste (TRUW) loads and potential contaminant releases at and en route to treatment, storage, and disposal sites in the US Department of Energy (DOE) complex are important considerations in DOE`s Waste Management Programmatic Environmental Impact Statement (WM PEIS). Waste loads are determined in part by the level of treatment the waste has undergone and the complex-wide configuration of origination, treatment, storage, and disposal sites selected for TRUW management. Other elements that impact waste loads are treatment volumes, waste characteristics, and the unit operation parameters of the treatment technologies. Treatment levels and site configurations have been combined into six TRUW management alternatives for study in the WM PEIS. This supplemental report to the WM PEIS gives the projected waste loads and contaminant release profiles for DOE treatment sites under each of the six TRUW management alternatives. It gives TRUW characteristics and inventories for current DOE generation and storage sites, describes the treatment technologies for three proposed levels of TRUW treatment, and presents the representative unit operation parameters of the treatment technologies. The data presented are primary inputs to developing the costs, health risks, and socioeconomic and environmental impacts of treating, packaging, and shipping TRUW for disposal.

  19. Best Demonstrated Available Technology (BDAT) for pollution control and waste treatment. (Latest citations from the NTIS bibliographic database). Published Search

    SciTech Connect (OSTI)

    Not Available

    1994-05-01

    The bibliography contains citations concerning the most advanced equipment and processes for pollution control and waste treatment according to the guidelines set by the Environmental Protection Agency (EPA). Citations discuss biological, thermal, physical, and chemical prosesses for the technology innovation, economic productivity, and environmental protection. Standards and regulations for gaseous, liquid, and solid pollution are included. Also discussed are water pollution control, food and pharmaceutical wastes, effluent treatment, and materials recovery. (Contains a minimum of 184 citations and includes a subject term index and title list.)

  20. Integrated Data Base for 1992: US spent fuel and radioactive waste inventories, projections, and characteristics. Revision 8

    SciTech Connect (OSTI)

    Payton, M. L.; Williams, J. T.; Tolbert-Smith, M.; Klein, J. A.

    1992-10-01

    The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1991. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal.

  1. Integrated Data Base report--1993: U.S. spent nuclear fuel and radioactive waste inventories, projections, and characteristics. Revision 10

    SciTech Connect (OSTI)

    Not Available

    1994-12-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and DOE spent nuclear fuel; also, commercial and US government-owned radioactive wastes through December 31, 1993. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program wastes, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 256 refs., 38 figs., 141 tabs.

  2. Load requirements for maintaining structural integrity of Hanford single-shell tanks during waste feed delivery and retrieval activities

    SciTech Connect (OSTI)

    JULYK, L.J.

    1999-09-22

    This document provides structural load requirements and their basis for maintaining the structural integrity of the Hanford Single-Shell Tanks during waste feed delivery and retrieval activities. The requirements are based on a review of previous requirements and their basis documents as well as load histories with particular emphasis on the proposed lead transfer feed tanks for the privatized vitrification plant.

  3. 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.

    2010-12-01

    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.

  4. Hanford Tank Waste Retrieval,

    Office of Environmental Management (EM)

    Tank Waste Retrieval, Treatment, and Disposition Framework September 24, 2013 U.S. Department of Energy Washington, D.C. 20585 Hanford Tank Waste Retrieval, Treatment, and...

  5. Engineering design and test plan for demonstrating DETOX treatment of mixed wastes

    SciTech Connect (OSTI)

    Goldblatt, S.; Dhooge, P.

    1995-03-01

    DETOX is a cocatalyzed wet oxidation process in which the catalysts are a relatively great concentration of iron ions (typically as iron(III) chloride) in the presence of small amounts of platinum and ruthenium ions. Organic compounds are oxidized completely to carbon dioxide, water, and (if chlorinated) hydrogen chloride. The process has shown promise as a non-thermal alternative to incineration for treatment and/or volume reduction of hazardous, radioactive, and mixed wastes. Design and fabrication of a demonstration unit capable of destroying 25. Kg/hr of organic material is now in progress. This paper describes the Title 2 design of the demonstration unit, and the planned demonstration effort at Savannah River Site (SRS) and Weldon Spring Site Remedial Action Project (WSSRAP).

  6. Borehole Summary Report for Waste Treatment Plant Seismic Borehole C4993

    SciTech Connect (OSTI)

    Rust, Colleen F.; Barnett, D. BRENT; Bowles, Nathan A.; Horner, Jake A.

    2007-02-28

    A core hole (C4998) and three boreholes (C4993, C4996, and C4997) were drilled to acquire stratigraphic and downhole seismic data to model potential seismic impacts and to refine design specifications and seismic criteria for the Waste Treatment Plant (WTP) under construction on the Hanford Site. Borehole C4993 was completed through the Saddle Mountains Basalt, the upper portion of the Wanapum Basalt, and associated sedimentary interbeds, to provide a continuous record of the rock penetrated by all four holes and to provide access to the subsurface for geophysical measure¬ment. Presented and compiled in this report are field-generated records for the deep mud rotary borehole C4993 at the WTP site. Material for C4993 includes borehole logs, lithologic summary, and record of rock chip samples collected during drilling through the months of August through early October. The borehole summary report also includes documentation of the mud rotary drilling, borehole logging, and sample collection.

  7. Excess Weapons Plutonium Disposition: Plutonium Packaging, Storage and Transportation and Waste Treatment, Storage and Disposal Activities

    SciTech Connect (OSTI)

    Jardine, L J; Borisov, G B

    2004-07-21

    A fifth annual Excess Weapons Plutonium Disposition meeting organized by Lawrence Livermore National Laboratory (LLNL) was held February 16-18, 2004, at the State Education Center (SEC), 4 Aerodromnya Drive, St. Petersburg, Russia. The meeting discussed Excess Weapons Plutonium Disposition topics for which LLNL has the US Technical Lead Organization responsibilities. The technical areas discussed included Radioactive Waste Treatment, Storage, and Disposal, Plutonium Oxide and Plutonium Metal Packaging, Storage and Transportation and Spent Fuel Packaging, Storage and Transportation. The meeting was conducted with a conference format using technical presentations of papers with simultaneous translation into English and Russian. There were 46 Russian attendees from 14 different Russian organizations and six non-Russian attendees, four from the US and two from France. Forty technical presentations were made. The meeting agenda is given in Appendix B and the attendance list is in Appendix C.

  8. 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.

    1992-09-01

    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.

  9. Microbiological characterization and specific methanogenic activity of anaerobe sludges used in urban solid waste treatment

    SciTech Connect (OSTI)

    Sandoval Lozano, Claudia Johanna Vergara Mendoza, Marisol; Carreno de Arango, Mariela; Castillo Monroy, Edgar Fernando

    2009-02-15

    This study presents the microbiological characterization of the anaerobic sludge used in a two-stage anaerobic reactor for the treatment of organic fraction of urban solid waste (OFUSW). This treatment is one alternative for reducing solid waste in landfills at the same time producing a biogas (CH{sub 4} and CO{sub 2}) and an effluent that can be used as biofertilizer. The system was inoculated with sludge from a wastewater treatment plant (WWTP) (Rio Frio Plant in Bucaramanga-Colombia) and a methanogenic anaerobic digester for the treatment of pig manure (Mesa de los Santos in Santander). Bacterial populations were evaluated by counting groups related to oxygen sensitivity, while metabolic groups were determined by most probable number (MPN) technique. Specific methanogenic activity (SMA) for acetate, formate, methanol and ethanol substrates was also determined. In the acidogenic reactor (R1), volatile fatty acids (VFA) reached values of 25,000 mg L{sup -1} and a concentration of CO{sub 2} of 90%. In this reactor, the fermentative population was predominant (10{sup 5}-10{sup 6} MPN mL{sup -1}). The acetogenic population was (10{sup 5} MPN mL{sup -1}) and the sulphate-reducing population was (10{sup 4}-10{sup 5} MPN mL{sup -1}). In the methanogenic reactor (R2), levels of CH{sub 4} (70%) were higher than CO{sub 2} (25%), whereas the VFA values were lower than 4000 mg L{sup -1}. Substrate competition between sulphate-reducing (10{sup 4}-10{sup 5} MPN mL{sup -1}) and methanogenic bacteria (10{sup 5} MPN mL{sup -1}) was not detected. From the SMA results obtained, acetoclastic (2.39 g COD-CH{sub 4} g{sup -1} VSS{sup -1} day{sup -1}) and hydrogenophilic (0.94 g COD-CH{sub 4} g{sup -1} VSS{sup -1} day{sup -1}) transformations as possible metabolic pathways used by methanogenic bacteria is suggested from the SMA results obtained. Methanotrix sp., Methanosarcina sp., Methanoccocus sp. and Methanobacterium sp. were identified.

  10. Department of Energy Idaho Operations Office evaluation of feasibility studies for private sector treatment of alpha and TRU mixed wastes

    SciTech Connect (OSTI)

    NONE

    1995-05-01

    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.

  11. Getting waste ready for shipment to the WIPP: integration of characterization and certification activities

    SciTech Connect (OSTI)

    Sinkule, B.; Knudsen, K.; Rogers, P.

    1996-06-01

    The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC) serve as the primary directive for assuring the safe handling, transportation, and disposal of transuranic (TRU) waste generated at Department of Energy (DOE) sites. The WIPP WAC address fulfillment of WIPP`s operational safety and performance assessment criteria, compliance with Resource Conservation and Recovery Act (RCRA) requirements, and preparation of waste packages that meet all transportation criteria. At individual generator sites, preparation of transuranic waste for final disposal at WIPP includes characterizing the waste to meet the requirements of the transuranic Waste Characterization Quality Assurance Program Plan (QAPP) and certifying waste containers to meet the WIPP WAC and the Transuranic Package Transporter-II Authorized Methods for Payload Control (TRAMPAC). This paper compares the quality assurance and quality control requirements specified in the WIPP WAC, QAPP, and TRAMPAC and discusses the potential to consolidate activities to comply with the TRU waste characterization and certification program requirements.

  12. Solid waste integrated forecast technical (SWIFT) report: FY1997 to FY 2070, Revision 1

    SciTech Connect (OSTI)

    Valero, O.J.; Templeton, K.J.; Morgan, J.

    1997-01-07

    This web site provides an up-to-date report on the radioactive solid waste expected to be managed by Hanford's Waste Management (WM) Project from onsite and offsite generators. It includes: an overview of Hanford-wide solid waste to be managed by the WM Project; program-level and waste class-specific estimates; background information on waste sources; and comparisons with previous forecasts and with other national data sources. This web site does not include: liquid waste (current or future generation); waste to be managed by the Environmental Restoration (EM-40) contractor (i.e., waste that will be disposed of at the Environmental Restoration Disposal Facility (ERDF)); or waste that has been received by the WM Project to date (i.e., inventory waste). The focus of this web site is on low-level mixed waste (LLMW), and transuranic waste (both non-mixed and mixed) (TRU(M)). Some details on low-level waste and hazardous waste are also provided. Currently, this web site is reporting data th at was requested on 10/14/96 and submitted on 10/25/96. The data represent a life cycle forecast covering all reported activities from FY97 through the end of each program's life cycle. Therefore, these data represent revisions from the previous FY97.0 Data Version, due primarily to revised estimates from PNNL. There is some useful information about the structure of this report in the SWIFT Report Web Site Overview.

  13. 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.

    1994-11-22

    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.

  14. 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)

    1994-01-01

    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.

  15. 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.

    2011-09-12

    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.

  16. 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

  17. Integrated data base for 1993: US spent fuel and radioactive waste inventories, projections, and characteristics. Revision 9

    SciTech Connect (OSTI)

    Klein, J.A.; Storch, S.N.; Ashline, R.C.

    1994-03-01

    The Integrated Data Base (IDB) Program has compiled historic data on inventories and characteristics of both commercial and DOE spent fuel; also, commercial and U.S. government-owned radioactive wastes through December 31, 1992. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest U.S. Department of Energy/Energy Information Administration (DOE/EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste (HLW), transuranic (TRU), waste, low-level waste (LLW), commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) LLW. For most of these categories, current and projected inventories are given through the calendar-year (CY) 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal.

  18. Vaporization of actinide oxides in thermal treatment processes for mixed waste

    SciTech Connect (OSTI)

    Ebbinghaus, B.B.; Krikorian, O.H.; Adamson, M.G.

    1994-10-04

    The purpose of this study is to evaluate the volatilities of U, Pu, and Am in thermal treatment processes for mixed wastes. The thermodynamics of vaporization U and Pu oxides in the presence of oxygen and water vapor and of U oxide in the presence of oxygen and chlorine were studied. Experimental studies of U oxide volatilities by previous authors have also been reviewed. For species where data are unavailable estimation methods were used to obtain free energies of formation of the gaseous species, The data are applied to thermal treatment processes in general and then more specifically to conditions representative of the Rocky Flats Plant Fluidized Bed Unit. (RFP FBU), molten salt oxidizer, and an incinerator. U volatilities are greatest ranging from 2.67 x 10{sup -7} gU/h in the RFP FBU to 4. 00 gU/h for typical incinerator conditions. Pu volatilities are almost 5 orders of magnitude less than U and Am volatilities are about 3 orders of magnitude less than Pu.

  19. Recommendations for developing and managing an integrated electronic waste policy & infrastructure in the Republic of Mauritius

    E-Print Network [OSTI]

    Ballal, Hrishikesh

    2009-01-01

    Electronic waste (e-waste) is a rapidly growing problem as well as a business opportunity given the huge volume that is generated. While there are a number policies and philosophies that guide end-of-life handling of ...

  20. Development Of A Macro-Batch Qualification Strategy For The Hanford Tank Waste Treatment And Immobilization Plant

    SciTech Connect (OSTI)

    Herman, Connie C.

    2013-09-30

    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.

  1. 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

    2013-07-01

    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)

  2. Wetland treatment of oil and gas well waste waters. Final report

    SciTech Connect (OSTI)

    Kadlec, R.; Srinivasan, K.

    1995-08-01

    Constructed wetlands are small on-site systems that possess three of the most desirable components of an industrial waste water treatment scheme: low cost, low maintenance and upset resistance. The main objective of the present study is to extend the knowledge base of wetland treatment systems to include processes and substances of particular importance to small, on-site systems receiving oil and gas well wastewaters. A list of the most relevant and comprehensive publications on the design of wetlands for water quality improvement was compiled and critically reviewed. Based on our literature search and conversations with researchers in the private sector, toxic organics such as Phenolics and b-naphthoic acid, (NA), and metals such as CU(II) and CR(VI) were selected as target adsorbates. A total of 90 lysimeters equivalent to a laboratory-scale wetland were designed and built to monitor the uptake and transformation of toxic organics and the immobilization of metal ions. Studies on the uptake of toxic organics such as phenol and b-naphthoic acid (NA) and heavy metals such as Cu(II) and Cr(VI), the latter two singly or as non-stoichiometric mixtures by laboratory-type wetlands (LWs) were conducted. These LWs were designed and built during the first year of this study. A road map and guidelines for a field-scale implementation of a wetland system for the treatment of oil and gas wastewaters have been suggested. Two types of wetlands, surface flow (SF) and sub surface flow (SSF), have been considered, and the relative merits of each configuration have been reviewed.

  3. REDUCING THE ENVIRONMENTAL IMPACT OF HIGH-DENSITY FISH PRODUCTION: AN INTEGRATED APPROACH TO SOLIDS TREATMENT FOR RECIRCULATING

    E-Print Network [OSTI]

    waste discharges, improve quality control, and reduce costs. The crucial processes that must aquaculture systems (RASs) allow for systematic optimization of the environmental variables that control that integrate two or more of these processes. Expandable granular biofilters (EGBs) integrate solids capture

  4. Technical Basis for Certification of Seismic Design Criteria for the Waste Treatment Plant, Hanford, Washington

    SciTech Connect (OSTI)

    Brouns, T.M.; Rohay, A.C. [Pacific Northwest National Laboratory, Richland, WA (United States); Youngs, R.R. [Geomatrix Consultants, Inc., Oakland, CA (United States); Costantino, C.J. [C.J. Costantino and Associates, Valley, NY (United States); Miller, L.F. [U.S. Department of Energy, Office of River Protection, Richland, WA (United States)

    2008-07-01

    In August 2007, Secretary of Energy Samuel W. Bodman approved the final seismic and ground motion criteria for the Waste Treatment and Immobilization Plant (WTP) at the Department of Energy's (DOE) Hanford Site. Construction of the WTP began in 2002 based on seismic design criteria established in 1999 and a probabilistic seismic hazard analysis completed in 1996. The design criteria were reevaluated in 2005 to address questions from the Defense Nuclear Facilities Safety Board (DNFSB), resulting in an increase by up to 40% in the seismic design basis. DOE announced in 2006 the suspension of construction on the pretreatment and high-level waste vitrification facilities within the WTP to validate the design with more stringent seismic criteria. In 2007, the U.S. Congress mandated that the Secretary of Energy certify the final seismic and ground motion criteria prior to expenditure of funds on construction of these two facilities. With the Secretary's approval of the final seismic criteria in the summer of 2007, DOE authorized restart of construction of the pretreatment and high-level waste vitrification facilities. The technical basis for the certification of seismic design criteria resulted from a two-year Seismic Boreholes Project that planned, collected, and analyzed geological data from four new boreholes drilled to depths of approximately 1400 feet below ground surface on the WTP site. A key uncertainty identified in the 2005 analyses was the velocity contrasts between the basalt flows and sedimentary interbeds below the WTP. The absence of directly-measured seismic shear wave velocities in the sedimentary interbeds resulted in the use of a wider and more conservative range of velocities in the 2005 analyses. The Seismic Boreholes Project was designed to directly measure the velocities and velocity contrasts in the basalts and sediments below the WTP, reanalyze the ground motion response, and assess the level of conservatism in the 2005 seismic design criteria. The characterization and analysis effort included 1) downhole measurements of the velocity properties (including uncertainties) of the basalt/interbed sequences, 2) confirmation of the geometry of the contact between the various basalt and interbedded sediments through examination of retrieved core from the core-hole and data collected through geophysical logging of each borehole, and 3) prediction of ground motion response to an earthquake using newly acquired and historic data. The data and analyses reflect a significant reduction in the uncertainty in shear wave velocities below the WTP and result in a significantly lower spectral acceleration (i.e., ground motion). The updated ground motion response analyses and corresponding design response spectra reflect a 25% lower peak horizontal acceleration than reflected in the 2005 design criteria. These results provide confidence that the WTP seismic design criteria are conservative. (authors)

  5. SARDINIA2003_2_Infrastructure.doc 1 Waste Treatment Infrastructure in North Rhine-Westphalia,

    E-Print Network [OSTI]

    Columbia University

    commercial and industrial waste management sector. For the turn of the year 2001/2002, this infrastructure Environmental Office of NRW (www.lua.nrw.de). 1. Introduction, characteristics of waste management in North responsibility and investment risk for appropriate waste management facilities. Favorable for the development

  6. Savannah River Site Tank 48H Waste Treatment Project Technology Readiness Assessment

    SciTech Connect (OSTI)

    Harmon, H.D.; Young, J.K.; Berkowitz, J.B.; DeVine, Jr.J.C.; Sutter, H.G.

    2008-07-01

    One of U.S. Department of Energy's (DOE) primary missions at Savannah River Site (SRS) is to retrieve and treat the high level waste (HLW) remaining in SRS tanks and close the F and H tank farms. At present, a significant impediment to timely completion of this mission is the presence of significant organic chemical contamination in Tank 48H. Tank 48H is a 1.3 million gallon tank with full secondary containment, located and interconnected within the SRS tank system. However, the tank has been isolated from the system and unavailable for use since 1983, because its contents - approximately 250,000 gallons of salt solution containing Cs-137 and other radioisotopes - are contaminated with nearly 22,000 Kg of tetraphenylborate, a material which can release benzene vapor to the tank head space in potentially flammable concentrations. An important element of the DOE SRS mission is to remove, process, and dispose of the contents of Tank 48H, both to eliminate the hazard it presents to the SRS H-Tank Farm and to return Tank 48H to service. Tank 48H must be returned to service to support operation of the Salt Waste Processing Facility, to free up HLW tank space, and to allow orderly tank closures per Federal Facility Agreement commitments. The Washington Savannah River Company (WSRC), the SRS prime contractor, has evaluated alternatives and selected two processes, Wet Air Oxidation (WAO) and Fluidized Steam Bed Reforming (FBSR) as candidates for Tank 48H processing. Over the past year, WSRC has been testing and evaluating these two processes, and DOE is nearing a final technology selection in late 2007. In parallel with WSRC's ongoing work, DOE convened a team of independent qualified experts to conduct a Technology Readiness Assessment (TRA). The purpose of the TRA was to determine the maturity level of the Tank 48H treatment technology candidates - WAO and FBSR. The methodology used for this TRA is based on detailed guidance for conducting TRAs contained in the Department of Defense (DoD), Technology Readiness Assessment Desk-book. The TRA consists of three parts: - Determination of the Critical Technology Elements (CTEs) for each of the candidate processes. - Evaluation of the Technology Readiness Levels (TRLs) of each CTE for each process. - Defining of the technology testing or engineering work necessary to bring immature technologies to the appropriate maturity levels. The TRA methodology assigns a TRL to a technology based on the lowest TRL assigned to any CTE of that technology. Based on the assessment, the overall TRL for WAO was 2 and the TRL for FBSR was 3. WAO was limited by the current lack of definition for the off-gas treatment system (TRL of 2). The FBSR Product Handling had little or no test work and therefore received the lowest score (TRL of 3) for the FBSR CTEs. In summary, both FBSR and WAO appear to be viable technologies for treatment of Tank 48H legacy waste. FBSR has a higher degree of maturity than WAO, but additional technology development will be required for both technologies. However, the Assessment Team believes that sufficient information is available for DOE to select the preferred or primary technology. Limited testing of the backup technology should be conducted as a risk mitigation strategy. (authors)

  7. SAVANNAH RIVER SITE TANK 48H WASTE TREATMENT PROJECT TECHNOLOGY READINESS ASSESSMENT

    SciTech Connect (OSTI)

    Harmon, Harry D.; Young, Joan K.; Berkowitz, Joan B.; Devine, John C.; Sutter, Herbert G.

    2008-10-25

    ABSTRACT One of U.S. Department of Energy’s (DOE) primary missions at Savannah River Site (SRS) is to retrieve and treat the high level waste (HLW) remaining in SRS tanks and close the F&H tank farms. At present, a significant impediment to timely completion of this mission is the presence of significant organic chemical contamination in Tank 48H. Tank 48H is a 1.3 million gallon tank with full secondary containment, located and interconnected within the SRS tank system. However, the tank has been isolated from the system and unavailable for use since 1983, because its contents – approximately 250,000 gallons of salt solution containing Cs-137 and other radioisotopes – are contaminated with nearly 22,000 Kg of tetraphenylborate, a material which can release benzene vapor to the tank head space in potentially flammable concentrations. An important element of the DOE SRS mission is to remove, process, and dispose of the contents of Tank 48H, both to eliminate the hazard it presents to the SRS H-Tank Farm and to return Tank 48H to service. Tank 48H must be returned to service to support operation of the Salt Waste Processing Facility, to free up HLW tank space, and to allow orderly tank closures per Federal Facility Agreement commitments. The Washington Savannah River Company (WSRC), the SRS prime contractor, has evaluated alternatives and selected two processes, Wet Air Oxidation (WAO) and Fluidized Steam Bed Reforming (FBSR) as candidates for Tank 48H processing. Over the past year, WSRC has been testing and evaluating these two processes, and DOE is nearing a final technology selection in late 2007. In parallel with WSRC’s ongoing work, DOE convened a team of independent qualified experts to conduct a Technology Readiness Assessment (TRA). The purpose of the TRA was to determine the maturity level of the Tank 48H treatment technology candidates – WAO and FBSR. The methodology used for this TRA is based on detailed guidance for conducting TRAs contained in the Department of Defense (DoD), Technology Readiness Assessment Deskbook. The TRA consists of three parts: • Determination of the Critical Technology Elements (CTEs) for each of the candidate processes. • Evaluation of the Technology Readiness Levels (TRLs) of each CTE for each process. • Defining of the technology testing or engineering work necessary to bring immature technologies to the appropriate maturity levels. The TRA methodology assigns a TRL to a technology based on the lowest TRL assigned to any CTE of that technology. Based on the assessment, the overall TRL for WAO was 2 and the TRL for FBSR was 3. WAO was limited by the current lack of definition for the off-gas treatment system (TRL of 2). The FBSR Product Handling had little or no test work and therefore received the lowest score (TRL of 3) for the FBSR CTEs. In summary, both FBSR and WAO appear to be viable technologies for treatment of Tank 48H legacy waste. FBSR has a higher degree of maturity than WAO, but additional technology development will be required for both technologies. However, the Assessment Team believes that sufficient information is available for DOE to select the preferred or primary technology. Limited testing of the backup technology should be conducted as a risk mitigation strategy.

  8. SAVANNAH RIVER SITE TANK 48H WASTE TREATMENT PROJECT TECHNOLOGY READINESS ASSESSMENT

    SciTech Connect (OSTI)

    Harmon, Harry D.; Young, Joan K.; Berkowitz, Joan B.; Devine, John C.; Sutter, Herbert G.

    2008-03-18

    One of U.S. Department of Energy's (DOE) primary missions at Savannah River Site (SRS) is to retrieve and treat the high level waste (HLW) remaining in SRS tanks and close the F&H tank farms. At present, a significant impediment to timely completion of this mission is the presence of significant organic chemical contamination in Tank 48H. Tank 48H is a 1.3 million gallon tank with full secondary containment, located and interconnected within the SRS tank system. However, the tank has been isolated from the system and unavailable for use since 1983, because its contents - approximately 250,000 gallons of salt solution containing Cs-137 and other radioisotopes - are contaminated with nearly 22,000 Kg of tetraphenylborate, a material which can release benzene vapor to the tank head space in potentially flammable concentrations. An important element of the DOE SRS mission is to remove, process, and dispose of the contents of Tank 48H, both to eliminate the hazard it presents to the SRS H-Tank Farm and to return Tank 48H to service. Tank 48H must be returned to service to support operation of the Salt Waste Processing Facility, to free up HLW tank space, and to allow orderly tank closures per Federal Facility Agreement commitments. The Washington Savannah River Company (WSRC), the SRS prime contractor, has evaluated alternatives and selected two processes, Wet Air Oxidation (WAO) and Fluidized Steam Bed Reforming (FBSR) as candidates for Tank 48H processing. Over the past year, WSRC has been testing and evaluating these two processes, and DOE is nearing a final technology selection in late 2007. In parallel with WSRC's ongoing work, DOE convened a team of independent qualified experts to conduct a Technology Readiness Assessment (TRA). The purpose of the TRA was to determine the maturity level of the Tank 48H treatment technology candidates - WAO and FBSR. The methodology used for this TRA is based on detailed guidance for conducting TRAs contained in the Department of Defense (DoD), Technology Readiness Assessment Deskbook. The TRA consists of three parts: (1) Determination of the Critical Technology Elements (CTEs) for each of the candidate processes. (2) Evaluation of the Technology Readiness Levels (TRLs) of each CTE for each process. (3) Defining of the technology testing or engineering work necessary to bring immature technologies to the appropriate maturity levels. The TRA methodology assigns a TRL to a technology based on the lowest TRL assigned to any CTE of that technology. Based on the assessment, the overall TRL for WAO was 2 and the TRL for FBSR was 3. WAO was limited by the current lack of definition for the off-gas treatment system (TRL of 2). The FBSR Product Handling had little or no test work and therefore received the lowest score (TRL of 3) for the FBSR CTEs. In summary, both FBSR and WAO appear to be viable technologies for treatment of Tank 48H legacy waste. FBSR has a higher degree of maturity than WAO, but additional technology development will be required for both technologies. However, the Assessment Team believes that sufficient information is available for DOE to select the preferred or primary technology. Limited testing of the backup technology should be conducted as a risk mitigation strategy.

  9. Agricultural, industrial and municipal waste management

    SciTech Connect (OSTI)

    Not Available

    1985-01-01

    It is right that consideration of the environment is of prime importance when agricultural and industrial processes are being developed. This book compiles the papers presented at the Institution of Mechanical Engineers conference. The contents include: The use of wastes for land reclamation and restoration; landfill, an environmentally acceptable method of waste disposal and an economic source of energy; control of leachate from waste disposal landfill sites using bentonite; landfill gas migration from operational landfill sites, monitoring and prevention; monitoring of emissions from hazardous waste incineration; hazardous wastes management in Hong Kong, a summary of a report and recommendations; the techniques and problems of chemical analysis of waste waters and leachate from waste tips; a small scale waste burning combustor; energy recovery from municipal waste by incineration; anaerobic treatment of industrial waste; a review of developments in the acid hydrolysis of cellulosic wastes; reduction of slag deposits by magnesium hydroxide injection; integrated rural energy centres (for agriculture-based economies); resource recovery; straw as a fuel in the UK; the computer as a tool for predicting the financial implications of future municipal waste disposal and recycling projects; solid wastes as a cement kiln fuel; monitoring and control of landfill gas; the utilization of waste derived fuels; the economics of energy recovery from municipal and industrial wastes; the development and construction of a municipal waste reclamation plant by a local authority.

  10. SECONDARY WASTE MANAGEMENT FOR HANFORD EARLY LOW ACTIVITY WASTE VITRIFICATION

    SciTech Connect (OSTI)

    UNTERREINER BJ

    2008-07-18

    More than 200 million liters (53 million gallons) of highly radioactive and hazardous waste is stored at the U.S. Department of Energy's Hanford Site in southeastern Washington State. The DOE's Hanford Site River Protection Project (RPP) mission includes tank waste retrieval, waste treatment, waste disposal, and tank farms closure activities. This mission will largely be accomplished by the construction and operation of three large treatment facilities at the Waste Treatment and Immobilization Plant (WTP): (1) a Pretreatment (PT) facility intended to separate the tank waste into High Level Waste (HLW) and Low Activity Waste (LAW); (2) a HLW vitrification facility intended to immobilize the HLW for disposal at a geologic repository in Yucca Mountain; and (3) a LAW vitrification facility intended to immobilize the LAW for shallow land burial at Hanford's Integrated Disposal Facility (IDF). The LAW facility is on target to be completed in 2014, five years prior to the completion of the rest of the WTP. In order to gain experience in the operation of the LAW vitrification facility, accelerate retrieval from single-shell tank (SST) farms, and hasten the completion of the LAW immobilization, it has been proposed to begin treatment of the low-activity waste five years before the conclusion of the WTP's construction. A challenge with this strategy is that the stream containing the LAW vitrification facility off-gas treatment condensates will not have the option of recycling back to pretreatment, and will instead be treated by the Hanford Effluent Treatment Facility (ETF). Here the off-gas condensates will be immobilized into a secondary waste form; ETF solid waste.

  11. 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.

    2014-08-21

    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

  12. K West Basin Integrated Water Treatment System (IWTS) E-F Annular Filter Vessel Accident Calculations

    SciTech Connect (OSTI)

    PIEPHO, M.G.

    2000-01-10

    Four bounding accidents postulated for the K West Basin integrated water treatment system are evaluated against applicable risk evaluation guidelines. The accidents are a spray leak during fuel retrieval, spray leak during backflushing a hydrogen explosion, and a fire breaching filter vessel and enclosure. Event trees and accident probabilities are estimated. In all cases, the unmitigated dose consequences are below the risk evaluation guidelines.

  13. K West Basin Integrated Water Treatment System (IWTS) E-F Annular Filter Vessel Accident Calculations

    SciTech Connect (OSTI)

    RITTMANN, P.D.

    1999-10-07

    Three bounding accidents postdated for the K West Basin integrated water treatment system are evaluated against applicable risk evaluation guidelines. The accidents are a spray leak during fuel retrieval, spray leak during backflushing, and a hydrogen explosion. Event trees and accident probabilities are estimated. In all cases, the unmitigated dose consequences are below the risk evaluation guidelines.

  14. Preliminary design report for the K basins integrated water treatment system

    SciTech Connect (OSTI)

    Pauly, T.R., Westinghouse Hanford

    1996-08-12

    This Preliminary Design Report (PDR) provides a revised concept for the K Basins Integrated Water Treatment Systems (IWTS). This PDR incorporates the 11 recommendations made in a May 1996 Value Engineering session into the Conceptual Design, and provides new flow diagrams, hazard category assessment, cost estimate, and schedule for the IWTS Subproject.

  15. Underground storage tank integrated demonstration: Evaluation of pretreatment options for Hanford tank wastes

    SciTech Connect (OSTI)

    Lumetta, G.J.; Wagner, M.J.; Colton, N.G.; Jones, E.O.

    1993-06-01

    Separation science plays a central role inn the pretreatment and disposal of nuclear wastes. The potential benefits of applying chemical separations in the pretreatment of the radioactive wastes stored at the various US Department of Energy sites cover both economic and environmental incentives. This is especially true at the Hanford Site, where the huge volume (>60 Mgal) of radioactive wastes stored in underground tanks could be partitioned into a very small volume of high-level waste (HLW) and a relatively large volume of low-level waste (LLW). The cost associated with vitrifying and disposing of just the HLW fraction in a geologic repository would be much less than those associated with vitrifying and disposing of all the wastes directly. Futhermore, the quality of the LLW form (e.g., grout) would be improved due to the lower inventory of radionuclides present in the LLW stream. In this report, we present the results of an evaluation of the pretreatment options for sludge taken from two different single-shell tanks at the Hanford Site-Tanks 241-B-110 and 241-U-110 (referred to as B-110 and U-110, respectively). The pretreatment options examined for these wastes included (1) leaching of transuranic (TRU) elements from the sludge, and (2) dissolution of the sludge followed by extraction of TRUs and {sup 90}Sr. In addition, the TRU leaching approach was examined for a third tank waste type, neutralized cladding removal waste.

  16. Microwave technology for waste management applications: Treatment of discarded electronic circuitry

    SciTech Connect (OSTI)

    Wicks, G.G. [Westinghouse Savannah River Technology Center, Aiken, SC (United States); Clark, D.E.; Schulz, R.L. [Univ. of Florida, Gainesville, FL (United States)

    1997-01-01

    Significant quantities of hazardous wastes are generated from a multitude of processes and products in today`s society. This waste inventory is not only very large and diverse, but is also growing at an alarming rate. In order to minimize the dangers presented by constituents in these wastes, microwave technologies are being investigated to render harmless the hazardous components and ultimately, to minimize their impact to individuals and the surrounding environment.

  17. Environmental Assessment and Finding of No Significant Impact: On-Site Treatment of Low Level Mixed Waste

    SciTech Connect (OSTI)

    N /A

    1999-03-22

    The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-1292) to evaluate the proposed treatment of low level mixed waste (LLMW) at the Rocky Flats Environmental Technology Site (Site). The purpose of the action is to treat LLMW in order to meet the Land Disposal Restrictions specified by the Resource Conservation and Recovery Act and the waste acceptance criteria of the planned disposal site(s). Approximately 17,000 cubic meters (m{sup 3}) of LLMW are currently stored at the Site. Another 65,000 m{sup 3}of LLMW are likely to be generated by Site closure activities (a total of 82,000 m{sup 3} of LLMW). About 35,000 m{sup 3} can be directly disposed of off-site without treatment, and most of the remaining 47,000 m{sup 3} of LLMW can be treated at off-site treatment, storage, and disposal facilities. However, some LLMW will require treatment on-site, either because it does not meet shipping requirements or because off-site treatment is not available for these particular types of LLMW. Currently, this LLMW is stored at the Site pending the development and implementation of effective treatment processes. The Site needs to treat this LLMW on-site prior to shipment to off-site disposal facilities, in order to meet the DOE long-term objective of clean up and closure of the Site. All on-site treatment of LLMW would comply with applicable Federal and State laws designed to protect public health and safety and to enhance protection of the environment. The EA describes and analyzes the environmental effects of the proposed action (using ten mobile treatment processes to treat waste on-site), and the alternatives of treating waste onsite (using two fixed treatment processes), and of taking no action. The EA was the subject of a public comment period from February 3 to 24, 1999. No written or other comments regarding the EA were received.

  18. Setting and Stiffening of Cementitious Components in Cast Stone Waste Form for Disposal of Secondary Wastes from the Hanford waste treatment and immobilization plant

    SciTech Connect (OSTI)

    Chung, Chul-Woo; Chun, Jaehun; Um, Wooyong; Sundaram, S. K.; Westsik, Joseph H.

    2013-04-01

    Cast stone is a cementitious waste form, a viable option to immobilize secondary nuclear liquid wastes generated from Hanford vitrification plant. While the strength and radioactive technetium leaching of different waste form candidates have been reported, no study has been performed to understand the flow and stiffening behavior of Cast Stone, which is essential to ensure the proper workability, especially considering necessary safety as a nuclear waste form in a field scale application. The rheological and ultrasonic wave reflection (UWR) measurements were used to understand the setting and stiffening Cast Stone batches. X-ray diffraction (XRD) was used to find the correlation between specific phase formation and the stiffening of the paste. Our results showed good correlation between rheological properties of the fresh Cast Stone mixture and phase formation during hydration of Cast Stone. Secondary gypsum formation originating from blast furnace slag was observed in Cast Stone made with low concentration simulants. The formation of gypsum was suppressed in high concentration simulants. It was found that the stiffening of Cast Stone was strongly dependent on the concentration of simulant. A threshold concentration for the drastic change in stiffening was found at 1.56 M Na concentration.

  19. Laboratory Report on Performance Evaluation of Key Constituents during Pre-Treatment of High Level Waste Direct Feed

    SciTech Connect (OSTI)

    Huber, Heinz J.

    2013-06-24

    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.

  20. 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)

    2005-07-01

    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.

  1. RESORCINOL-FORMALDEHYDE ION EXCHANGE RESIN CHEMISTRY FOR HIGH LEVEL WASTE TREATMENT

    SciTech Connect (OSTI)

    Nash, C.; Duignan, M.

    2010-01-14

    A principal goal at the Savannah River Site is to safely dispose of the large volume of liquid nuclear waste held in many storage tanks. In-tank ion exchange technology is being considered for cesium removal using a polymer resin made of resorcinol formaldehyde that has been engineered into microspheres. The waste under study is generally lower in potassium and organic components than Hanford waste; therefore, the resin performance was evaluated with actual dissolved salt waste. The ion exchange performance and resin chemistry results are discussed.

  2. 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; Corcoran, Connie

    2012-11-15

    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.

  3. Status and integration of studies of gas generation in Hanford wastes

    SciTech Connect (OSTI)

    Pederson, L.R.; Bryan, S.A.

    1996-10-01

    The purpose of this report is to review recent progress in determining the mechanism, kinetics, and stoichiometry of gas generation in Hanford waste tanks. Information has been gathered from the results of (1) laboratory studies with simulated wastes; (2) laboratory studies with actual waste core samples (Tanks SY-101 and SY-103); (3) studies of thermal and radiolytic reactions in the gas phase; (4) gas solubility evaluations; and (5) in-tank gas composition data. The results of laboratory studies using simulated wastes, which were aimed at determining chemical mechanisms responsible for gas generation, are summarized in Section 2. Emphasized are findings from work performed at the Georgia Institute of Technology (GIT), which was conducted under subcontract to Pacific Northwest National Laboratory (PNNL) and completed in FY 1996. Thermally activated pathways for the decomposition of hydroxyethylethylene-diaminetriacetic acid (HEDTA, trisodium salt) in simulated wastes were established by this work, among other accomplishments.

  4. A JOULE-HEATED MELTER TECHNOLOGY FOR THE TREATMENT AND IMMOBILIZATION OF LOW-ACTIVITY WASTE

    SciTech Connect (OSTI)

    KELLY SE

    2011-04-07

    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.

  5. FLUIDIZED BED STEAM REFORMING FOR TREATMENT AND IMMOBILIZATION OF LOW-ACTIVITY WASTE

    SciTech Connect (OSTI)

    HEWITT WM

    2011-04-08

    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.

  6. BULK VITRIFICATION TECHNOLOGY FOR THE TREATMENT AND IMMOBILIZATION OF LOW-ACTIVITY WASTE

    SciTech Connect (OSTI)

    ARD KE

    2011-04-11

    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.

  7. RCRA Permit for a Hazardous Waste Management Facility, Permit Number NEV HW0101, Annual Summary/Waste Minimization Report

    SciTech Connect (OSTI)

    Arnold, Patrick

    2014-02-14

    This report summarizes the EPA identification number of each generator from which the Permittee received a waste stream, a description and quantity of each waste stream in tons and cubic feet received at the facility, the method of treatment, storage, and/or disposal for each waste stream, a description of the waste minimization efforts undertaken, a description of the changes in volume and toxicity of waste actually received, any unusual occurrences, and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101.

  8. Treatment of metal-laden hazardous wastes with advanced clean coal technology by-products. Quarterly report, March 30, 1996--June 30, 1996

    SciTech Connect (OSTI)

    Cobb, J.T. Jr.; Neufeld, R.D.; Blachere, J.R. [and others

    1998-04-01

    Progress is described on the use of by-products form clean coal technologies for the treatment of hazardous wastes. During the third quarter of Phase 2, work continued on evaluating Phase 1 samples (including evaluation of a seventh waste), conducting scholarly work, preparing for field work, preparing and delivering presentations, and making additional outside contacts.

  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. Treatment of waste by the Molten Salt Oxidation process at the Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Crosley, S.M.; Lorenzo, D.K.; Van Cleve, J.E. [Oak Ridge National Lab., TN (United States); Gay, R.L.; Barclay, K.M.; Newcomb, J.C.; Yosim, S.J. [Rockwell International Corp., Canoga Park, CA (United States)

    1993-03-01

    The Molten Salt Oxidation (MSO) process has been under development by the Energy Technology Engineering Center (ETEC) to treat hazardous, radioactive, and mixed waste. Testing of the system was done on a number of wastes to demonstrate the technical feasibility of the process. This testing included simulated intermediate level waste (ILW) from the Oak Ridge National Laboratory. The intermediate level waste stream consisted of a slurry of concentrated aqueous solutions of sodium hydroxide and sodium nitrate, with a small amount of miscellaneous combustible components (PVC, TBP, kerosene, and ion exchange resins). The purpose of these tests was to evaluate the destruction of the organics, evaporation of the water, and conversion of the hazardous salts (hydroxide and nitrate) to non-hazardous sodium carbonate. Results of the tests are discussed and analyzed, and the possibilities of applying the MSO process to different waste streams at ORNL in the future are explored.

  11. Laboratory Testing of Bulk Vitrified Low-Activity Waste Forms to Support the 2005 Integrated Disposal Facility Performance Assessment

    SciTech Connect (OSTI)

    Pierce, Eric M.; McGrail, B. Peter; Bagaasen, Larry M.; Rodriguez, Elsa A.; Wellman, Dawn M.; Geiszler, Keith N.; Baum, Steven R.; Reed, Lunde R.; Crum, Jarrod V.; Schaef, Herbert T.

    2006-06-30

    The purpose of this report is to document the results from laboratory testing of the bulk vitri-fied (BV) waste form that was conducted in support of the 2005 integrated disposal facility (IDF) performance assessment (PA). Laboratory testing provides a majority of the key input data re-quired to assess the long-term performance of the BV waste package with the STORM code. Test data from three principal methods, as described by McGrail et al. (2000a; 2003a), are dis-cussed in this testing report including the single-pass flow-through test (SPFT) and product con-sistency test (PCT). Each of these test methods focuses on different aspects of the glass corrosion process. See McGrail et al. (2000a; 2003a) for additional details regarding these test methods and their use in evaluating long-term glass performance. In addition to evaluating the long-term glass performance, this report discusses the results and methods used to provided a recommended best estimate of the soluble fraction of 99Tc that can be leached from the engineer-ing-scale BV waste package. These laboratory tests are part of a continuum of testing that is aimed at improving the performance of the BV waste package.

  12. Laboratory Testing of Bulk Vitrified Low-Activity Waste Forms to Support the 2005 Integrated Disposal Facility Performance Assessment

    SciTech Connect (OSTI)

    Pierce, Eric M.; McGrail, B. Peter; Bagaasen, Larry M.; Rodriguez, Elsa A.; Wellman, Dawn M.; Geiszler, Keith N.; Baum, Steven R.; Reed, Lunde R.; Crum, Jarrod V.; Schaef, Herbert T.

    2005-03-31

    The purpose of this report is to document the results from laboratory testing of the bulk vitri-fied (BV) waste form that was conducted in support of the 2005 integrated disposal facility (IDF) performance assessment (PA). Laboratory testing provides a majority of the key input data re-quired to assess the long-term performance of the BV waste package with the STORM code. Test data from three principal methods, as described by McGrail et al. (2000a; 2003a), are dis-cussed in this testing report including the single-pass flow-through test (SPFT) and product con-sistency test (PCT). Each of these test methods focuses on different aspects of the glass corrosion process. See McGrail et al. (2000a; 2003a) for additional details regarding these test methods and their use in evaluating long-term glass performance. In addition to evaluating the long-term glass performance, this report discusses the results and methods used to provided a recommended best estimate of the soluble fraction of 99Tc that can be leached from the engineer-ing-scale BV waste package. These laboratory tests are part of a continuum of testing that is aimed at improving the performance of the BV waste package.

  13. Updated Site Response Analyses for the Waste Treatment Plant, DOE Hanford, Site, Washington.

    SciTech Connect (OSTI)

    Youngs, Robert R.

    2007-06-29

    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.

  14. Development of a pilot safety information document (PSID) for the replacement of radioactive liquid waste treatment facility at Los Alamos National Laboratory 

    E-Print Network [OSTI]

    Selvage, Ronald Derek

    1995-01-01

    Radioactive Liquid Waste Treatment Facility. The PSID documents risk analysis for the proposed facility and some of the alternatives, accident analysis, radioactive and hazardous material doses to off-site individuals, and the cumulative safety risk from...

  15. Investigation of separation, treatment, and recycling options for hazardous paint blast media waste. Final report

    SciTech Connect (OSTI)

    Boy, J.H.; Race, T.D.; Reinbold, K.A.

    1996-02-01

    U.S. Army depot depaint operations generate over 4 million kg per year of contaminated paint blast media wastes. The objective of this work was to investigate technologies that might significantly mitigate this Army hazardous waste disposal problem. Most of the technologies investigated either failed to meet acceptable TCLP levels for hazardous metals content, or failed to meet Army disposal requirements. However, based on a review of several commercially available services, it is recommended that Army depot depaint operations consider processing hazardous blast media waste through properly regulated contractors that offer safe, effective, and economical stabilization, fixation, and recycling technologies.

  16. Integrated electronic waste management in Mexico : law, technology and public policy

    E-Print Network [OSTI]

    Gonzalez Llera, Ricardo, 1971-

    2004-01-01

    What is electronic waste? Why is it considered a problem? What are the public health implications of its mishandling? The electronic industry, a sector that has experienced one of the highest growth rates of the last decade, ...

  17. Waste Form Release Calculations for the 2005 Integrated Disposal Facility Performance Assessment

    SciTech Connect (OSTI)

    Bacon, Diana H.; McGrail, B PETER.

    2005-07-26

    A set of reactive chemical transport calculations was conducted with the Subsurface Transport Over Reactive Multiphases (STORM) code to evaluate the long-term performance of a representative low-activity waste glass in a shallow subsurface disposal system located on the Hanford Site. Two-dimensional simulations were run until the waste form release rates reached a quasi-stationary-state, usually after 2,000 to 4,000 yr. The primary difference between the waste form release simulations for the 2001 ILAW PA, and the simulations described herein, is the number of different materials considered. Whereas the previous PA considered only LAWABP1 glass, the current PA also describes radionuclide release from three different WTP glasses (LAWA44, LAWB45 and LAWC22), two different bulk vitrification glasses (6-tank composite and S-109), and three different grout waste forms (containing Silver Iodide, Barium Iodide and Barium Iodate). All WTP and bulk vitrification glasses perform well. However, the radionuclide release from the salt in the cast refractory surrounding the bulk vitrification waste packages is 2 to 170 times higher than the glass release rate, depending on the water recharge rate. Iodine-129 release from grouted waste forms is highly sensitive to the solubility of the iodine compound contained in the grout. The normalized iodine release rate from grout containing barium iodate is a factor of 10 higher than what the normalized release rate would be if the iodine were contained in LAWA44 glass.

  18. Technical area status report for waste destruction and stabilization

    SciTech Connect (OSTI)

    Dalton, J.D.; Harris, T.L.; DeWitt, L.M.

    1993-08-01

    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/activities throughout the DOE complex. In order to successfully achieve the goal of properly managing waste and the cleanup of the DOE sites, the EM was divided into five organizations: the Office of Planning and Resource Management (EM-10); the Office of Environmental Quality Assurance and Resource Management (EM-20); the Office of Waste Operations (EM-30); the Office of Environmental Restoration (EM-40); and the Office of Technology and Development (EM-50). The mission of the Office of Technology Development (OTD) is to develop treatment technologies for DOE`s operational and environmental restoration wastes where current treatment technologies are inadequate or not available. The Mixed Waste Integrated Program (MWIP) was created by OTD to assist in the development of treatment technologies for the DOE mixed low-level wastes (MLLW). The MWIP has established five Technical Support Groups (TSGs) whose purpose is to identify, evaluate, and develop treatment technologies within five general technical areas representing waste treatment functions from initial waste handling through generation of final waste forms. These TSGs are: (1) Front-End Waste Handling, (2) Physical/Chemical Treatment, (3) Waste Destruction and Stabilization, (4) Second-Stage Destruction and Offgas Treatment, and (5) Final Waste Forms. This report describes the functions of the Waste Destruction and Stabilization (WDS) group. Specifically, the following items are discussed: DOE waste stream identification; summary of previous efforts; summary of WDS treatment technologies; currently funded WDS activities; and recommendations for future activities.

  19. Comparative analysis of composting as a municipal solid waste treatment process in India

    E-Print Network [OSTI]

    Liu, Yeqing

    2015-01-01

    A study of composting municipal solid waste (MSW) in India compared a specific facility in Muzaffarnagar, Uttar Pradesh, India to existing standards and practices documented in literature globally and in other facilities ...

  20. 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...

  1. Expedited demonstration of molten salt mixed waste treatment technology. Final report

    SciTech Connect (OSTI)

    1995-02-02

    This final report discusses the molten salt mixed waste project in terms of the various subtasks established. Subtask 1: Carbon monoxide emissions; Establish a salt recycle schedule and/or a strategy for off-gas control for MWMF that keeps carbon monoxide emission below 100 ppm on an hourly averaged basis. Subtask 2: Salt melt viscosity; Experiments are conducted to determine salt viscosity as a function of ash composition, ash concentration, temperature, and time. Subtask 3: Determine that the amount of sodium carbonate entrained in the off-gas is minimal, and that any deposited salt can easily be removed form the piping using a soot blower or other means. Subtask 4: The provision of at least one final waste form that meets the waste acceptance criteria of a landfill that will take the waste. This report discusses the progress made in each of these areas.

  2. EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste

    Broader source: Energy.gov [DOE]

    This EIS  evaluates the potential environmental and cost impacts of strategic managment alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue...

  3. Public acceptability of the use of gamma rays from spent nuclear fuel as a hazardous waste treatment process

    SciTech Connect (OSTI)

    Mincher, B.J.; Wells, R.P.; Reilly, H.J.

    1992-01-01

    Three methods were used to estimate public reaction to the use of gamma irradiation of hazardous wastes as a hazardous waste treatment process. The gamma source of interest is spent nuclear fuel. The first method is Benefit-Risk Decision Making, where the benefits of the proposed technology are compared to its risks. The second analysis compares the proposed technology to the other, currently used nuclear technologies and estimates public reaction based on that comparison. The third analysis is called Analysis of Public Consent, and is based on the professional methods of the Institute for Participatory Management and Planning. The conclusion of all three methods is that the proposed technology should not result in negative public reaction sufficient to prevent implementation.

  4. An integrated systems approach to remote retrieval of buried transuranic waste using a telerobotic transport vehicle, innovative end effector, and remote excavator

    SciTech Connect (OSTI)

    Smith, A.M.; Rice, P.; Hyde, R. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); Peterson, R. [RAHCO International, Spokane, WA (United States)

    1995-02-01

    Between 1952 and 1970, over two million cubic feet of transuranic mixed waste was buried in shallow pits and trenches in the Subsurface Disposal Area at the Idaho National Engineering Laboratory Radioactive Waste Management Complex. Commingled with this two million cubic feet of waste is up to 10 million cubic feet of fill soil. The pits and trenches were constructed similarly to municipal landfills with both stacked and random dump waste forms such as barrels and boxes. The main contaminants are micron-sized particles of plutonium and americium oxides, chlorides, and hydroxides. Retrieval, treatment, and disposal is one of the options being considered for the waste. This report describes the results of a field demonstration conducted to evaluate technologies for excavating, and transporting buried transuranic wastes at the INEL, and other hazardous or radioactive waste sites throughout the US Department of Energy complex. The full-scale demonstration, conduced at RAHCO Internationals facilities in Spokane, Washington, in the summer of 1994, evaluated equipment performance and techniques for digging, dumping, and transporting buried waste. Three technologies were evaluated in the demonstration: an Innovative End Effector for dust free dumping, a Telerobotic Transport Vehicle to convey retrieved waste from the digface, and a Remote Operated Excavator to deploy the Innovative End Effector and perform waste retrieval operations. Data were gathered and analyzed to evaluate retrieval performance parameters such as retrieval rates, transportation rates, human factors, and the equipment`s capability to control contamination spread.

  5. Waste Management Project fiscal year 1998 multi-year work plan, WBS 1.2

    SciTech Connect (OSTI)

    Jacobsen, P.H.

    1997-09-23

    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 disposal of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project, Liquid Effluents Project, and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible.

  6. Development of a new process for treatment of paint sludge wastes. Final report, May 1986-December 1987

    SciTech Connect (OSTI)

    Balasco, A.A.; Bodek, I.; Goldman, M.E.; Mazrimas, M.J.; Rossetti, M.

    1987-12-31

    This report presents the results of laboratory tests performed on paint-waste samples obtained from the Letterkenny Army Depot (LEAD). The purpose of these tests was to determine if the ash residue from a thermal-treatment process such as combustion would be classified as hazardous according to the Environmental Protection Agency (EPA) Toxicity Characteristic Leaching Procedure (TCLP). In addition, the feasibility of generating a glassified product from the ash which would be classified as non-hazardous was also tested. Finally, tests were also performed to determine if recovery of selected metals from the ash is feasible. The results of the laboratory program suggest that thermal treatment of paint waste under some conditions may be feasible for generation of non-hazardous ash residue. Further experiments on a pilot-scale are recommended, however, to investigate this approach to determine the need for subsequent treatment (e.g., glassification and/or recovery) of the ash product and the actual destruction efficiency of organic components.

  7. Using wastes as resources

    SciTech Connect (OSTI)

    Prakasam, T.B.S.; Lue-Hing, C. )

    1992-09-01

    The collection, treatment, and disposal of domestic and industrial wastewater, garbage, and other wastes present considerable problems in urban and semiurban areas of developing countries. Major benefits of using integrated treatment and resource recovery systems include waste stabilization, recovering energy as biogas, producing food from algae and fish, irrigation, improved public health, and aquatic weed control and use. Information and research are needed, however, to assesss the appropriateness, benefits, and limitations of such technology on a large scale. System configuration depends on the types and quantities of wastes available for processing. There must be enough collectable waste for the system to be viable. Information should be gathered to asses whether there is a net public health benefit by implementing a waste treatment and resource recovery system. Benefits such as savings in medical expenses and increased worker productivity due to improved health may be difficult to quantify. The potential health risks created by implementing a resource recovery system should be studied. The most difficult issues to contend with are socioeconomic in nature. Often, the poor performance of a proven technology is attributed to a lack of proper understanding of its principles by the operators, lack of community interest, improper operator training, and poor management. Public education to motivate people to accept technologies that are beneficial to them is important.

  8. Aqueous nitrate waste treatment: Technology comparison, cost/benefit, and market analysis

    SciTech Connect (OSTI)

    Not Available

    1994-01-01

    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.

  9. Integrated data base report--1995: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    SciTech Connect (OSTI)

    1996-12-01

    The information in this report summarizes the U.S. Department of Energy (DOE) data base for inventories, projections, and characteristics of domestic spent nuclear fuel and radioactive waste. This report is updated annually to keep abreast of continual waste inventory and projection changes in both the government and commercial sectors. Baseline information is provided for DOE program planning purposes and to support DOE program decisions. Although the primary purpose of this document is to provide background information for program planning within the DOE community, it has also been found useful by state and local governments, the academic community, and some private citizens.

  10. Integrating Volume Reduction and Packaging Alternatives to Achieve Cost Savings for Low Level Waste Disposal at the Rocky Flats Environmental Technology Site

    SciTech Connect (OSTI)

    Church, A.; Gordon, J.; Montrose, J. K.

    2002-02-26

    In order to reduce costs and achieve schedules for Closure of the Rocky Flats Environmental Technology Site (RFETS), the Waste Requirements Group has implemented a number of cost saving initiatives aimed at integrating waste volume reduction with the selection of compliant waste packaging methods for the disposal of RFETS low level radioactive waste (LLW). Waste Guidance Inventory and Shipping Forecasts indicate that over 200,000 m3 of low level waste will be shipped offsite between FY2002 and FY2006. Current projections indicate that the majority of this waste will be shipped offsite in an estimated 40,000 55-gallon drums, 10,000 metal and plywood boxes, and 5000 cargo containers. Currently, the projected cost for packaging, shipment, and disposal adds up to $80 million. With these waste volume and cost projections, the need for more efficient and cost effective packaging and transportation options were apparent in order to reduce costs and achieve future Site packaging a nd transportation needs. This paper presents some of the cost saving initiatives being implemented for waste packaging at the Rocky Flats Environmental Technology Site (the Site). There are many options for either volume reduction or alternative packaging. Each building and/or project may indicate different preferences and/or combinations of options.

  11. SPONTANEOUS CATALYTIC WET AIR OXIDATION DURING PRE-TREATMENT OF HIGH-LEVEL RADIOACTIVE WASTE SLUDGE

    SciTech Connect (OSTI)

    Koopman, D.; Herman, C.; Pareizs, J.; Bannochie, C.; Best, D.; Bibler, N.; Fellinger, T.

    2009-10-01

    Savannah River Remediation, LLC (SRR) operates the Defense Waste Processing Facility for the U.S. Department of Energy at the Savannah River Site. This facility immobilizes high-level radioactive waste through vitrification following chemical pretreatment. Catalytic destruction of formate and oxalate ions to carbon dioxide has been observed during qualification testing of non-radioactive analog systems. Carbon dioxide production greatly exceeded hydrogen production, indicating the occurrence of a process other than the catalytic decomposition of formic acid. Statistical modeling was used to relate the new reaction chemistry to partial catalytic wet air oxidation of both formate and oxalate ions driven by the low concentrations of palladium, rhodium, and/or ruthenium in the waste. Variations in process conditions led to increases or decreases in the total oxidative destruction, as well as partially shifting the preferred species undergoing destruction from oxalate ion to formate ion.

  12. Task 1.6 -- Mixed waste treatment. Semi-annual report, January 1--June 30, 1995

    SciTech Connect (OSTI)

    Rindt, J.R.

    1997-08-01

    Mixed-waste sites make up the majority of contaminated sites, yet remediation techniques used at such sites often target only the most prevalent contaminant. A better understanding of site situation (i.e., most common types of contamination), current remediation techniques, and combinations of techniques would provide insight into areas in which further research should be performed. The first half of this task program year consisted of a survey of common types of mixed-wastes sites and a detailed literature search of the remediation techniques and combinations of techniques that were currently available. From this information, an assessment of each of the techniques was made and combined into various ways appropriate to mixed-waste protocol. This activity provided insight into areas in which further research should be performed.

  13. Westinghouse Waste Simulation and Optimization Software Tool - 13493

    SciTech Connect (OSTI)

    Mennicken, Kim [Westinghouse Electric Germany GmbH, Global Waste Management, Dudenstrasse 44, D-68167 Mannheim (Germany)] [Westinghouse Electric Germany GmbH, Global Waste Management, Dudenstrasse 44, D-68167 Mannheim (Germany); 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)

    2013-07-01

    Radioactive waste is produced during NPP operation and NPP D and D. Different kinds of waste with different volumes and properties have to be treated. Finding a technically and commercially optimized waste treatment concept is a difficult and time consuming process. The Westinghouse waste simulation and optimization software tool is an approach to study the total life cycle cost of any waste management facility. The tool enables the user of the simulation and optimization software to plan processes and storage buildings and to identify bottlenecks in the overall waste management design before starting detailed planning activities. Furthermore, application of the software enables the user to optimize the number of treatment systems, to determine the minimum design capacity for onsite storage facilities, to identify bottlenecks in the overall design and to identify the most cost-effective treatment paths by maintaining optimal waste treatment technologies. In combination with proven waste treatment equipment and integrated waste management solutions, the waste simulation and optimization software provides reliable qualitative results that lead to an effective planning and minimization of the total project planning risk of any waste management activity. (authors)

  14. FINANCING ELECTRONIC WASTE RECYCLING - Californian Households’ Willingness to Pay Advanced Recycling Fees

    E-Print Network [OSTI]

    Nixon, Hilary; Saphores, Jean-Daniel M

    2007-01-01

    California Integrated Waste Management Board. CIWMB, 2004.California Integrated Waste Management Board. CIWMB, 2006.California Integrated Waste Management Board. Accessed June

  15. Yucca Mountain project canister material corrosion studies as applied to the electrometallurgical treatment metallic waste form

    SciTech Connect (OSTI)

    Keiser, D.D.

    1996-11-01

    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.

  16. Endpointtool: An Excel{sup R}-Based Workbook for Hanford Tank Waste Treatment Planning

    SciTech Connect (OSTI)

    Agnew, S.F. [Nuclear Waste Consulting, San Diego, CA (United States); Corbin, R.A.; Anderson, M. [Columbia Energy and Environmental Services, Inc., Richland, WA (United States)

    2008-07-01

    The EndpointTool is a Microsoft Excel{sup R}-based workbook with a set of macros and worksheets for the evaluation of Hanford Site tank treatment scenarios. This tool enables the user to determine bottlenecks in processes and storage and address regulatory issues. It also provides an avenue to evaluate new technologies, as well as changes in existing technologies and their impact to the current baseline. The EndpointTool tracks 46 radionuclides, 52 species, and 10 properties for each event. Seventeen different processes are modeled, each with its own worksheet that describes that process, has its assumptions, qualifications, and calculations, and holds the historical results of each process event. This enables the user to not only look at the big picture, but to evaluate process parameters such as flowrates, sizing, etc. The user composes an event that is a combination of a sender tank, a process tank, and a receiver tank. Each event involves one of the processes and each process can have up to a total of 81 assumptions and 180 qualifications. The starting point for all tank inventories is the Hanford tank Best-Basis Inventory (BBI). Each tank comprises up to three phases: salt-cake, sludge, and supernatant. Each of these BBI phases has an insoluble solids fraction that was derived from the embedded solubility model. Each composed event must meet a set of qualifications that are dependent on the process, as well as whether the sender tank has any inventory, whether the receiver tank has sufficient space, etc. For example, supernatant events are limited to a maximum solids specified in its assumptions, usually 5 wt%. Above this solids contents, a slurry transfer must be used. Once a qualified event is added to the Event List, the inventories of involved tanks are updated in a status worksheet and the results of that event appear in the timeline and metrics charts. Although the EndpointTool is not a true dynamic model, it provides a useful desktop capability for quite complex process sequences. While only schedule and variances are presently performed, a cost module is in development. In summary: The EndpointTool is a powerful Excel-based planning resource. It is portable and test runs have shown that about 600 Events can effectively represent the processing of all of Hanford tank waste. Since each Event takes approximately 3 seconds to run on a 1.8 GHz CPU with 512 MB ram, a complete run only takes approximately 30 minutes. As a result, extensive scenario planning and process optimization is possible with this tool. Moreover, Event List 'scenarios' can be easily shared among users and scenario planning can then be distributed among a large number of users. (authors)

  17. Zr electrorefining process for the treatment of cladding hull waste in LiCl-KCl molten salts

    SciTech Connect (OSTI)

    Lee, Chang Hwa; Lee, You Lee; Jeon, Min Ku; Kang, Kweon Ho; Choi, Yong Taek; Park, Geun Il [Korea Atomic Energy Research Institute - KAERI, 989-111 Daeduk-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)

    2013-07-01

    Zr electrorefining for the treatment of Zircaloy-4 cladding hull waste is demonstrated in LiCl-KCl-ZrCl{sub 4} molten salts. Although a Zr oxide layer thicker than 5 ?m strongly inhibits the Zr dissolution process, pre-treatment processes increases the dissolution kinetics. For 10 g-scale experiments, the purities of the recovered Zr were 99.54 wt.% and 99.74 wt.% for fresh and oxidized cladding tubes, respectively, with no electrical contact issue. The optimal condition for Zr electrorefining has been found to improve the morphological feature of the recovered Zr, which reduces the salt incorporation by examining the effect of the process parameters such as the ZrCl{sub 4} concentration and the applied potential.

  18. An Integrated Water Treatment Technology Solution for Sustainable Water Resource Management in the Marcellus Shale

    SciTech Connect (OSTI)

    Matthew Bruff; Ned Godshall; Karen Evans

    2011-04-30

    This Final Scientific/ Technical Report submitted with respect to Project DE-FE0000833 titled 'An Integrated Water Treatment Technology Solution for Sustainable Water Resource Management in the Marcellus Shale' in support of final reporting requirements. This final report contains a compilation of previous reports with the most current data in order to produce one final complete document. The goal of this research was to provide an integrated approach aimed at addressing the increasing water resource challenges between natural gas production and other water stakeholders in shale gas basins. The objective was to demonstrate that the AltelaRain{reg_sign} technology could be successfully deployed in the Marcellus Shale Basin to treat frac flow-back water. That objective has been successfully met.

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

    SciTech Connect (OSTI)

    VAN BEEK JE

    2008-02-14

    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.

  20. Guidance manual for the identification of hazardous wastes delivered to publicly owned treatment works by truck, rail, or dedicated pipe

    SciTech Connect (OSTI)

    Not Available

    1987-06-01

    The manual is directed towards two types of facilities: First, guidance is to POTWs that wish to preclude the entry of hazardous wastes into their facilities and avoid regulation and liability under RCRA. Administrative/technical recommendations for control of such wastes is provided, many of which are already in use by POTWs. Second, the responsibilities of POTWs that choose to accept hazardous wastes from truck, rail, or dedicated pipeline are discussed, including relevant regulatory provisions, strict liability and corrective action requirements for releases, and recommended procedures for waste acceptance/management. The manual describes the RCRA regulatory status of wastes that POTW operators typically may encounter. The manual includes a Waste Monitoring Plan. Appendices give the following: RCRA lists; RCRA listed hazardous wastes; examples of POTW sewer use ordinance language, waste hauler permit; waste tracking form, notification of hazardous waste activity; uniform hazardous waste manifest; biennial hazardous waste report; and state hazardous waste contacts.

  1. Coke oven gas treatment and by-product plant of Magnitogorsk Integrated Iron and Steel Works

    SciTech Connect (OSTI)

    Egorov, V.N.; Anikin, G.J. [Magnitogorsk Integrated Iron and Steel Works, (Russian Federation); Gross, M. [Krupp Koppers GmbH, Essen (Germany)

    1995-12-01

    Magnitogorsk Integrated Iron and Steel Works, Russia, decided to erect a new coke oven gas treatment and by-product plant to replace the existing obsolete units and to improve the environmental conditions of the area. The paper deals with the technological concept and the design requirements. Commissioning is scheduled at the beginning of 1996. The paper describes H{sub 2}S and NH{sub 3} removal, sulfur recovery and ammonia destruction, primary gas cooling and electrostatic tar precipitation, and the distributed control system that will be installed.

  2. Office of River Protection (DOE-ORP) Hanford Tank Waste Treatment Alternatives March 2000

    SciTech Connect (OSTI)

    WODRICH, D.D.

    2000-03-24

    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.

  3. RCRA Permit for a Hazardous Waste Management Facility Permit Number NEV HW0101 Annual Summary/Waste Minimization Report Calendar Year 2012, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    Arnold, P. M.

    2013-02-21

    This report summarizes the U.S. Environmental Protection Agency (EPA) identification number of each generator from which the Permittee received a waste stream, a description and quantity of each waste stream in tons and cubic feet received at the facility, the method of treatment, storage, and/or disposal for each waste stream, a description of the waste minimization efforts undertaken, a description of the changes in volume and toxicity of waste actually received, any unusual occurrences, and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101, issued 10/17/10.

  4. RCRA Permit for a Hazardous Waste Management Facility Permit Number NEV HW0101 Annual Summary/Waste Minimization Report Calendar Year 2011

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2012-02-16

    This report summarizes the U.S. Environmental Protection Agency (EPA) identification number of each generator from which the Permittee received a waste stream; a description and quantity of each waste stream in tons and cubic feet received at the facility; the method of treatment, storage, and/or disposal for each waste stream; a description of the waste minimization efforts undertaken; a description of the changes in volume and toxicity of waste actually received; any unusual occurrences; and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101.

  5. Waste Treatment and Immobilization Plant U. S. Department of Energy Office of River Protection Submerged Bed Scrubber Condensate Disposition Project - 13460

    SciTech Connect (OSTI)

    Yanochko, Ronald M. [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); Corcoran, Connie [AEM Consulting, LLC, 1201 Jadwin Avenue, Richland, Washington 99352 (United States)] [AEM Consulting, LLC, 1201 Jadwin Avenue, Richland, Washington 99352 (United States)

    2013-07-01

    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 [1]. 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 [2]. This study evaluated alternatives for direct off-site disposal of this SBS without pre-treatment, which mitigates potential issues associated with recycling. This study [2] concluded that SBS direct disposal is a viable option to the WTP baseline. The results show: - Off-site transportation and disposal of the SBS condensate is achievable and cost effective. - Reduction of approximately 4,325 vitrified WTP Low Activity Waste canisters could be realized. - Positive WTP operational impacts; minimal WTP construction impacts are realized. - Reduction of mass flow from the LAW Facility to the Pretreatment Facility by 66%. - Improved Double Shell Tank (DST) space management is a benefit. (authors)

  6. An Overview of Project Planning for Hot-Isostatic Pressure Treatment of High-Level Waste Calcine for the Idaho Cleanup Project - 12289

    SciTech Connect (OSTI)

    Nenni, Joseph A.; Thompson, Theron J.

    2012-07-01

    The Calcine Disposition Project is responsible for retrieval, treatment by hot-isostatic pressure, packaging, and disposal of highly radioactive calcine stored at the Idaho Nuclear Technology and Engineering Center at the Idaho National Laboratory Site in southeast Idaho. In the 2009 Amended Record of Decision: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement the Department of Energy documented the selection of hot-isostatic pressure as the technology to treat the calcine. The Record of Decision specifies that the treatment results in a volume-reduced, monolithic waste form suitable for transport outside of Idaho by a target date of December 31, 2035. That target date is specified in the 1995 Idaho Settlement Agreement to treat and prepare the calcine for transport out of Idaho in exchange for allowing storage of Navy spent nuclear fuel at the INL Site. The project is completing the design of the calcine-treatment process and facility to comply with Record of Decision, Settlement Agreement, Idaho Department of Environmental Quality, and Department of Energy requirements. A systems engineering approach is being used to define the project mission and requirements, manage risks, and establish the safety basis for decision making in compliance with DOE O 413.3B, 'Program and Project Management for the Acquisition of Capital Assets'. The approach draws heavily on 'design-for-quality' tools to systematically add quality, predict design reliability, and manage variation in the earliest possible stages of design when it is most efficient. Use of these tools provides a standardized basis for interfacing systems to interact across system boundaries and promotes system integration on a facility-wide basis. A mass and energy model was developed to assist in the design of process equipment, determine material-flow parameters, and estimate process emissions. Data generated from failure modes and effects analysis and reliability, availability, maintainability, and inspectability analysis were incorporated into a time and motion model to validate and verify the capability to complete treatment of the calcine within the required schedule. The Calcine Disposition Project systems engineering approach, including use of industry-proven design-for-quality tools and quantitative assessment techniques, has strengthened the project's design capability to meet its intended mission in a safe, cost-effective, and timely manner. Use of these tools has been particularly helpful to the project in early design planning to manage variation; improve requirements and high-consequence risk management; and more effectively apply alternative, interface, failure mode, RAMI, and time and motion analyses at the earliest possible stages of design when their application is most efficient and cost effective. The project is using these tools to design and develop HIP treatment of highly radioactive calcine to produce a volume-reduced, monolithic waste form with immobilization of hazardous and radioactive constituents. (authors)

  7. CHALLENGES WITH RETRIEVING TRANSURANIC WASTE FROM THE HANFORD BURIAL GROUNDS

    SciTech Connect (OSTI)

    SWAN, R.J.; LAKES, M.E.

    2007-08-06

    The U.S. DOE's Hanford Reservation produced plutonium and other nuclear materials for the nation's defense starting in World War II. The defense mission generated wastes that were either retrievably stored (i.e. retrievably stored waste) and/or disposed of in burial grounds. Challenges have emerged from retrieving suspect TRU waste including adequacy of records, radiological concerns, container integrity, industrial hygiene and safety issues, the lack of processing/treatment facilities, and the integration of regulatory requirements. All retrievably stored waste is managed as mixed waste and assumed to be TRU waste, unless documented otherwise. Mixed waste is defined as radioactive waste that contains hazardous constituents. The Atomic Energy Act governs waste with radionuclides, and the Resource Conservation and Recovery Act (RCRA) governs waste with hazardous constituents. Waste may also be governed by the Toxic Substances Control Act (TSCA), and a portion may be managed under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). In 1970, TRU waste was required to be placed in 20-year retrievable storage and segregated from other Waste. Prior to that date, segregation did not occur. Because of the changing definition of TRU over the years, and the limitations of early assay equipment, all retrievably stored waste in the burial grounds is managed as suspect TRU. Experience has shown that some of this waste will be characterized as low-level (non-TRU) waste after assay. The majority of the retrieved waste is not amenable to sampling due to waste type and/or radiological issues. Key to waste retrieval and disposition are characterization, historical investigation and research, knowledge of past handling and packaging, as well as a broad understanding and application of the regulations.

  8. EIS-0200: Waste Management Programmatic Environmental Impact...

    Office of Environmental Management (EM)

    00: Waste Management Programmatic Environmental Impact Statement for Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste EIS-0200: Waste Management...

  9. Electrochemical/Pyrometallurgical Waste Stream Processing and Waste Form Fabrication

    SciTech Connect (OSTI)

    Steven Frank; Hwan Seo Park; Yung Zun Cho; William Ebert; Brian Riley

    2015-07-01

    This report summarizes treatment and waste form options being evaluated for waste streams resulting from the electrochemical/pyrometallurgical (pyro ) processing of used oxide nuclear fuel. The technologies that are described are South Korean (Republic of Korea – ROK) and United States of America (US) ‘centric’ in the approach to treating pyroprocessing wastes and are based on the decade long collaborations between US and ROK researchers. Some of the general and advanced technologies described in this report will be demonstrated during the Integrated Recycle Test (IRT) to be conducted as a part of the Joint Fuel Cycle Study (JFCS) collaboration between US Department of Energy (DOE) and ROK national laboratories. The JFCS means to specifically address and evaluated the technological, economic, and safe guard issues associated with the treatment of used nuclear fuel by pyroprocessing. The IRT will involve the processing of commercial, used oxide fuel to recover uranium and transuranics. The recovered transuranics will then be fabricated into metallic fuel and irradiated to transmutate, or burn the transuranic elements to shorter lived radionuclides. In addition, the various process streams will be evaluated and tested for fission product removal, electrolytic salt recycle, minimization of actinide loss to waste streams and waste form fabrication and characterization. This report specifically addresses the production and testing of those waste forms to demonstrate their compatibility with treatment options and suitability for disposal.

  10. SEAMIST{trademark} in-situ instrumentation and vapor sampling system applications in the Sandia Mixed Waste Landfill Integrated Demonstration program: Final report

    SciTech Connect (OSTI)

    Williams, C.; Lowry, W.; Cremer, D.; Dunn, S.D.

    1995-09-01

    The Mixed Waste Landfill Integrated Demonstration was tasked with demonstrating innovative technologies for the cleanup of chemical and mixed waste landfills that are representive of sites occurring throughout the DOE complex and the nation. The SEAMIST{trademark} inverting membrane deployment system has been used successfully at the Mixed Waste Landfill Integrated Demonstration (MWLID) for multipoint vapor sampling, pressure measurement, permeability measurement, sensor integration demonstrations, and borehole lining. Several instruments were deployed inside the SEAMIST{trademark}-lined boreholes to detect metals, radionuclides, moisture, and geologic variations. The liner protected the instruments from contamination, maintained support of the uncased borehole wall, and sealed the total borehole from air circulation. Recent activities included the installation of three multipoint vapor sampling systems and sensor integration systems in 100-foot-deep vertical boreholes. A long term pressure monitoring program has recorded barometric pressure effects at depth with relatively high spatial resolution. The SEAMIST{trademark} system has been integrated with a variety of hydrologic and chemical sensors for in-situ measurements, demonstrating its versatility as an instrument deployment system that allows easy emplacement and removal. Standard SEAMIST{trademark} vapor sampling systems were also integrated with state-of-the-art volatile organic compound analysis technologies. The results and status of these demonstration tests are presented.

  11. 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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergyTher i nAandSummary From: v2.7|Energy ResponseCall:BeyondConsequenceWasteSite

  12. 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.

    1983-03-01

    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.

  13. Integrated renewable energy/organic waste recycling system. Final report, July 31, 1982

    SciTech Connect (OSTI)

    Hamburg, R.A.; Davenport, S.

    1982-01-01

    Two operating systems for integrated recycling of organic materials are described. The systems include Chinese water-pressure design biogas digesters/solar greenhouses/and algae and aquatic plant ponds-all in passive symbiotic relationships with a minimum of technological sophistication. Economic, Financial and Net Energy Analyses of these systems have been done with concern toward long term environmental effects. A discussion of fish ponds and fuel alcohol production is also included since they offer much potential for expanded integration. 21 tabs.

  14. Assessment of sludge management options in a waste water treatment plant

    E-Print Network [OSTI]

    Lim, Jong hyun, M. Eng. Massachusetts Institute of Technology

    2012-01-01

    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 ...

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

    SciTech Connect (OSTI)

    Sylvester, Paul; Milner, Tim; Ruffing, Jennifer; Poole, Scott; Townson, Paul; Jensen, Jesse

    2013-07-01

    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)

  16. Feasibility study for thermal treatment of solid tire wastes in Bangladesh by using pyrolysis technology

    SciTech Connect (OSTI)

    Islam, M.R.; Joardder, M.U.H.; Hasan, S.M.; Takai, K.; Haniu, H.

    2011-09-15

    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.

  17. 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.

    1996-08-01

    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.

  18. Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC) : gap analysis for high fidelity and performance assessment code development.

    SciTech Connect (OSTI)

    Lee, Joon H.; Siegel, Malcolm Dean; Arguello, Jose Guadalupe, Jr.; Webb, Stephen Walter; Dewers, Thomas A.; Mariner, Paul E.; Edwards, Harold Carter; Fuller, Timothy J.; Freeze, Geoffrey A.; Jove-Colon, Carlos F.; Wang, Yifeng

    2011-03-01

    This report describes a gap analysis performed in the process of developing the Waste Integrated Performance and Safety Codes (IPSC) in support of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The goal of the Waste IPSC is to develop an integrated suite of computational modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with rigorous verification, validation, and software quality requirements. The gap analyses documented in this report were are performed during an initial gap analysis to identify candidate codes and tools to support the development and integration of the Waste IPSC, and during follow-on activities that delved into more detailed assessments of the various codes that were acquired, studied, and tested. The current Waste IPSC strategy is to acquire and integrate the necessary Waste IPSC capabilities wherever feasible, and develop only those capabilities that cannot be acquired or suitably integrated, verified, or validated. The gap analysis indicates that significant capabilities may already exist in the existing THC codes although there is no single code able to fully account for all physical and chemical processes involved in a waste disposal system. Large gaps exist in modeling chemical processes and their couplings with other processes. The coupling of chemical processes with flow transport and mechanical deformation remains challenging. The data for extreme environments (e.g., for elevated temperature and high ionic strength media) that are needed for repository modeling are severely lacking. In addition, most of existing reactive transport codes were developed for non-radioactive contaminants, and they need to be adapted to account for radionuclide decay and in-growth. The accessibility to the source codes is generally limited. Because the problems of interest for the Waste IPSC are likely to result in relatively large computational models, a compact memory-usage footprint and a fast/robust solution procedure will be needed. A robust massively parallel processing (MPP) capability will also be required to provide reasonable turnaround times on the analyses that will be performed with the code. A performance assessment (PA) calculation for a waste disposal system generally requires a large number (hundreds to thousands) of model simulations to quantify the effect of model parameter uncertainties on the predicted repository performance. A set of codes for a PA calculation must be sufficiently robust and fast in terms of code execution. A PA system as a whole must be able to provide multiple alternative models for a specific set of physical/chemical processes, so that the users can choose various levels of modeling complexity based on their modeling needs. This requires PA codes, preferably, to be highly modularized. Most of the existing codes have difficulties meeting these requirements. Based on the gap analysis results, we have made the following recommendations for the code selection and code development for the NEAMS waste IPSC: (1) build fully coupled high-fidelity THCMBR codes using the existing SIERRA codes (e.g., ARIA and ADAGIO) and platform, (2) use DAKOTA to build an enhanced performance assessment system (EPAS), and build a modular code architecture and key code modules for performance assessments. The key chemical calculation modules will be built by expanding the existing CANTERA capabilities as well as by extracting useful components from other existing codes.

  19. EFFICIENCY OF THREE REACTIVE MIXTURES OF ORGANIC WASTES FOR THE TREATMENT OF

    E-Print Network [OSTI]

    Aubertin, Michel

    ACID MINE DRAINAGE C. Neculita 1 , G.J. Zagury 1 , B. Bussičre 2,3 1 Department of Civil, Geological-reducing bacteria (SRB) are a reasonable alternative technology for acid mine drainage (AMD) treatment drainage minier acide (DMA). Afin d'ętre efficaces, ils nécessitent une source de carbone organique

  20. Waste Management Facilities cost information for mixed low-level waste. Revision 1

    SciTech Connect (OSTI)

    Shropshire, D.; Sherick, M.; Biadgi, C.

    1995-06-01

    This report contains preconceptual designs and planning level life-cycle cost estimates for managing mixed low-level waste. The report`s information on treatment, storage, and disposal modules can be integrated to develop total life-cycle costs for various waste management options. A procedure to guide the US Department of Energy and its contractor personnel in the use of cost estimation data is also summarized in this report.

  1. Path integral treatment of a family of super-integrable systems in n-dimensional Euclidean space

    E-Print Network [OSTI]

    M. T. Chefrour; F. Benamira; L. Guechi; S. Mameri

    2003-09-14

    The exact path integration for a family of maximally super-integrable systems generalizing the hydrogen atom in the $n$-dimensional Euclidean space is presented. The Green's function is calculated in parabolic rotational and spherical coordinate systems. The energy spectrum and the correctly normalized wave functions of the bound states are obtained from the poles of the Green's function and their residues, respectively.

  2. Experimental data and analysis to support the design of an ion-exchange process for the treatment of Hanford tank waste supernatant liquids

    SciTech Connect (OSTI)

    Kurath, D.E.; Bray, L.A.; Brooks, K.P.; Brown, G.N.; Bryan, S.A.; Carlson, C.D.; Carson, K.J.; DesChane, J.R.; Elovich, R.J.; Kim, A.Y.

    1994-12-01

    Hanford`s 177 underground storage tanks contain a mixture of sludge, salt cake, and alkaline supernatant liquids. Disposal options for these wastes are high-level waste (HLW) glass for disposal in a repository or low-level waste (LLW) glass for onsite disposal. Systems-engineering studies show that economic and environmental considerations preclude disposal of these wastes without further treatment. Difficulties inherent in transportation and disposal of relatively large volumes of HLW make it impossible to vitrify all of the tank waste as HLW. Potential environmental impacts make direct disposal of all of the tank waste as LLW glass unacceptable. Although the pretreatment and disposal requirements are still being defined, most pretreatment scenarios include retrieval of the aqueous liquids, dissolution of the salt cakes, and washing of the sludges to remove soluble components. Most of the cesium is expected to be in the aqueous liquids, which are the focus of this report on cesium removal by ion exchange. The main objectives of the ion-exchange process are removing cesium from the bulk of the tank waste (i.e., decontamination) and concentrating the separated cesium for vitrification. Because exact requirements for removal of {sup 137}Cs have not yet been defined, a range of removal requirements will be considered. This study addresses requirements to achieve {sup 137}Cs levels in LLW glass between (1) the Nuclear Regulatory Commission (NRC) Class C (10 CFR 61) limit of 4600 Ci/m{sup 3} and (2) 1/10th of the NRC Class A limit of 1 Ci/m{sup 3} i.e., 0.1/m{sup 3}. The required degrees of separation of cesium from other waste components is a complex function involving interactions between the design of the vitrification process, waste form considerations, and other HLW stream components that are to be vitrified.

  3. The need for a characteristics-based approach to radioactive waste classification as informed by advanced nuclear fuel cycles using the fuel-cycle integration and tradeoffs (FIT) model

    SciTech Connect (OSTI)

    Djokic, D. [Department of Nuclear Engineering, University of California, Berkeley, 3115B Etcheverry Hall, Berkeley, CA 94720-1730 (United States); Piet, S.; Pincock, L.; Soelberg, N. [Idaho National Laboratory - INL, 2525 North Fremont Avenue, Idaho Falls, ID 83415 (United States)

    2013-07-01

    This study explores the impact of wastes generated from potential future fuel cycles and the issues presented by classifying these under current classification criteria, and discusses the possibility of a comprehensive and consistent characteristics-based classification framework based on new waste streams created from advanced fuel cycles. A static mass flow model, Fuel-Cycle Integration and Tradeoffs (FIT), was used to calculate the composition of waste streams resulting from different nuclear fuel cycle choices. Because heat generation is generally the most important factor limiting geological repository areal loading, this analysis focuses on the impact of waste form heat load on waste classification practices, although classifying by metrics of radiotoxicity, mass, and volume is also possible. Waste streams generated in different fuel cycles and their possible classification based on the current U.S. framework and international standards are discussed. It is shown that the effects of separating waste streams are neglected under a source-based radioactive waste classification system. (authors)

  4. 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

    2012-01-30

    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.

  5. 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.

    1998-02-03

    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.

  6. Waste treatment by ion-exchange. (Latest citations from Pollution abstracts). Published Search

    SciTech Connect (OSTI)

    NONE

    1995-09-01

    The bibliography contains citations concerning wastewater treatment by ion-exchange techniques. Methods for removing metals, nitrates, phosphates, fluorides, and organic pollutants are described. Applications of this technology to the electroplating, metal finishing, pulp, paper, and other industries are included. The citations examine the commercial feasibility of using ion-exchange methods for pollutant reduction when the process is used alone or in combination with various pretreatment techniques. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

  7. Waste treatment by ion-exchange. (Latest citations from Pollution abstracts). Published Search

    SciTech Connect (OSTI)

    NONE

    1996-10-01

    The bibliography contains citations concerning wastewater treatment by ion-exchange techniques. Methods for removing metals, nitrates, phosphates, fluorides, and organic pollutants are described. Applications of this technology to the electroplating, metal finishing, pulp, paper, and other industries are included. The citations examine the commercial feasibility of using ion-exchange methods for pollutant reduction when the process is used alone or in combination with various pretreatment techniques. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

  8. The effect of high pH chemical hydrolysis on biological waste treatment 

    E-Print Network [OSTI]

    Smullen, Richard Frederick

    1971-01-01

    CO&. The reduction in plant size makes the cost with regeneration comparable to an activated sludge plant that must incinerate its sludge. It should also be noted that Buzzell and Sawyer (4) reported that lime sludge stored 4-7 days at pH greater than 11. 0 did... helpful suggestions throughout the study. Dr. William D. Langley, and Dr. Chia Shun Shih, for serving on my my committee. Vi TABLE OF CONTENTS INTRODUCTION REVIEW OF LITFRATURE Chemical Treatment . Lime Sludge Characteristics Non...

  9. Indicators of waste management efficiency related to different territorial conditions

    SciTech Connect (OSTI)

    Passarini, Fabrizio, E-mail: fabrizio.passarini@unibo.it [University of Bologna, Dept. Industrial Chemistry and Materials, viale Risorgimento 4, I-40136 Bologna (Italy); Vassura, Ivano, E-mail: ivano.vassura@unibo.it [University of Bologna, Dept. Industrial Chemistry and Materials, viale Risorgimento 4, I-40136 Bologna (Italy); Monti, Francesco, E-mail: fmonti84@gmail.com [University of Bologna, Dept. Industrial Chemistry and Materials, viale Risorgimento 4, I-40136 Bologna (Italy); Morselli, Luciano, E-mail: luciano.morselli@unibo.it [University of Bologna, Dept. Industrial Chemistry and Materials, viale Risorgimento 4, I-40136 Bologna (Italy); Villani, Barbara, E-mail: bvillani@arpa.emr.it [Regional Environmental Protection Agency (Emilia-Romagna Region), Largo Caduti del Lavoro 6, I-40122 Bologna (Italy)

    2011-04-15

    The amount of waste produced and the control of separate collection are crucial issues for the planning of a territorial Integrated Waste Management System, enabling the allocation of each sorted waste fraction to the proper treatment and recycling processes. The present study focuses on assessing indicators of different waste management systems in areas characterized by different territorial conditions. The investigated case study concerns the municipalities of Emilia Romagna (northern Italy), which present a rather uniform socioeconomic situation, but a variety of geographic, urban and waste management characteristics. A survey of waste generation and collection rates was carried out, and correlated with the different territorial conditions, classifying the municipalities according to altitude and population density. The best environmental performances, in terms of high separate collection rate, were found on average in rural areas in the plain, while the lowest waste generation was associated with rural hill towns.

  10. Treatment of metal-laden hazardous wastes with advanced clean coal technology by-products. Quarterly report, June 30--September 30, 1996

    SciTech Connect (OSTI)

    Cobb, J.T.; Neufeld, R.D.; Blachere, J.R. [and others

    1996-12-31

    During the fourth quarter of Phase 2, work continued on evaluating treatment of the seventh residue of Phase 1, conducting scholarly work, preparing for field work, preparing and delivering presentations, and making additional outside contacts. The work consisted of further testing of the solidification of the seventh hazardous waste--the sandblast residue from paint removal in a building--and examining the microstructure of the products of solidification. There were two treated waste mixtures which demonstrated immediate stabilization, the sandblast residue w/30% spray drier residue (CONSOL) and the sandblast residue w/50% PFBC residue (Tidd).

  11. Treatment of metal-laden hazardous wastes with advanced clean coal technology by-products. Quarterly report, December 30, 1996--March 30, 1997

    SciTech Connect (OSTI)

    NONE

    1997-12-31

    The objective of this project is to utilize coal ashes to process hazardous materials such as industrial waste water treatment residues, contaminated soils, and air pollution control dusts from the metal industry and municipal waste incineration. This report describes the activities of the project team during the reporting period. The principal work has focused upon continuing evaluation of aged samples from Phase 1, planning supportive laboratory studies for Phase 2, completing scholarly work, reestablishing MAX Environmental Technologies, Inc., as the subcontractor for the field work of Phase 2, proposing two presentations for later in 1997, and making and responding to several outside contacts.

  12. Materials and Fuels Complex Hazardous Waste Management Act/Resource Conservation and Recovery Act Storage and Treatment Permit Reapplication, Environmental Protection Agency Number ID4890008952

    SciTech Connect (OSTI)

    Holzemer, Michael J.; Hart, Edward

    2015-04-01

    Hazardous Waste Management Act/Resource Conservation and Recovery Act Storage and Treatment Permit Reapplication for the Idaho National Laboratory Materials and Fuels Complex Hazardous Waste Management Act/Resource Conservation and Recovery Act Partial Permit, PER-116. This Permit Reapplication is required by the PER-116 Permit Conditions I.G. and I.H., and must be submitted to the Idaho Department of Environmental Quality in accordance with IDAPA 58.01.05.012 [40 CFR §§ 270.10 and 270.13 through 270.29].

  13. A Characteristics-Based Approach to Radioactive Waste Classification in Advanced Nuclear Fuel Cycles

    E-Print Network [OSTI]

    Djokic, Denia

    2013-01-01

    in   better   nuclear   waste   management  and  disposal  fuel   cycles  on  nuclear  waste  management  and  waste  Nuclear   Fuel,”   Integrated   Radioactive   Waste   Management  

  14. Transforming trash: reuse as a waste management and climate change mitigation strategy

    E-Print Network [OSTI]

    Vergara, Sintana Eugenia

    2011-01-01

    P. 2001. Integrated Solid Waste Management: A Life CyclePeter. 2001. Integrated Solid Waste Management: A Life Cycleof privatization of solid waste management on the Zabaleen

  15. Transforming trash: reuse as a waste management and climate change mitigation strategy

    E-Print Network [OSTI]

    Vergara, Sintana Eugenia

    2011-01-01

    Integrated Solid Waste Management: A Life Cycle Inventory.Integrated Solid Waste Management: A Life Cycle Inventory.right choice for waste management in developing countries. ”

  16. An overview of the sustainability of solid waste management at military installations

    E-Print Network [OSTI]

    Borglin, S.

    2010-01-01

    Developing Integrated Solid Waste Management Plans at ArmyDeveloping Integrated Solid Waste Management Plans at Armyoil in diesel engines." Waste Management In Press, Corrected

  17. Waste management project fiscal year 1998 multi-year work plan WBS 1.2

    SciTech Connect (OSTI)

    Slaybaugh, R.R.

    1997-08-29

    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.

  18. An Introduction to Virginia Tech's Waste Management Program

    E-Print Network [OSTI]

    ;Waste Management Program · Montgomery Regional Solid Waste Authority (MRSWA): · Provides integrated solid waste management for the New River Valley Region · Located in Christiansburg, VA · Materials;Waste Management Program · Non-Municipal Solid Waste Recycled MATERIAL DESCRIPTION SOURCE RESPONSIBLE

  19. Parametric Optimization of the MEO Process for Treatment of Mixed Waste Residues

    SciTech Connect (OSTI)

    Cournoyer, M.E.; Smith, W.H.

    1999-02-28

    A series of bench-scale experiments were conducted to determine the optimum reaction conditions for destruction of styrene-divinyl benzene based cation resin and methylene chloride by the mediated electrochemical oxidation (MEO) process. Reaction parameters examined include choice of electron transfer mediator, reaction temperature and solvent system. For the cation exchange resins, maximum destruction efficiencies were obtained using cerium (IV) as mediator in nitric acid at a temperature of 70 C. Reasonable efficiencies were also realized with silver(II) and cobalt (III) at ambient temperature in the same solvent. Use of sulfuric acid as the solvent yielded much lower efficiencies under equivalent conditions. Methylene chloride was found to react only with silver (II) at ambient temperature in nitric acid media, cobalt (III) and cerium (IV) were totally ineffective. These results demonstrate a need to perform bench-scale experiments to determine optimum operating conditions for each organic substrate targeted for treatment by the MEO process.

  20. SOLID WASTE INTEGRATED FORECAST TECHNICAL (SWIFT) REPORT FY2005 THRU FY2035 2005.0 VOLUME 2

    SciTech Connect (OSTI)

    BARCOT, R.A.

    2005-08-17

    This report provides up-to-date life cycle information about the radioactive solid waste expected to be managed by Hanford's Waste Management (WM) Project from onsite and offsite generators. It includes: (1) an overview of Hanford-wide solid waste to be managed by the WM Project; (2) multi-level and waste class-specific estimates; (3) background information on waste sources; and (4) comparisons to previous forecasts and other national data sources. The focus of this report is low-level waste (LLW), mixed low-level waste (MLLW), and transuranic waste, both non-mixed and mixed (TRU(M)). Some details on hazardous waste are also provided, however, this information is not considered comprehensive. This report includes data requested in December, 2004 with updates through March 31,2005. The data represent a life cycle forecast covering all reported activities from FY2005 through the end of each program's life cycle and are an update of the previous FY2004.1 data version.

  1. Hanford’s Supplemental Treatment Project: Full-Scale Integrated Testing of In-Container-Vitrification and a 10,000-Liter Dryer

    SciTech Connect (OSTI)

    Witwer, Keith S.; Dysland, Eric J.; Garfield, J. S.; Beck, T. H.; Matyas, Josef; Bagaasen, Larry M.; Cooley, Scott K.; Pierce, Eric M.; Kim, Dong-Sang; Schweiger, Michael J.

    2008-02-22

    The GeoMelt® In-Container Vitrification™ (ICV™) process was selected by the U.S. Department of Energy (DOE) in 2004 for further evaluation as the supplemental treatment technology for Hanford’s low-activity waste (LAW). Also referred to as “bulk vitrification,” this process combines glass forming minerals, LAW, and chemical amendments; dries the mixture; and then vitrifies the material in a refractory-lined steel container. AMEC Nuclear Ltd. (AMEC) is adapting its GeoMelt ICV™ technology for this application with technical and analytical support from Pacific Northwest National Laboratory (PNNL). The DVBS project is funded by the DOE Office of River Protection and administered by CH2M HILL Hanford Group, Inc. The Demonstration Bulk Vitrification Project (DBVS) was initiated to engineer, construct, and operate a full-scale bulk vitrification pilot-plant to treat up to 750,000 liters of LAW from Waste Tank 241-S-109 at the DOE Hanford Site. Since the beginning of the DBVS project in 2004, testing has used laboratory, crucible-scale, and engineering-scale equipment to help establish process limitations of selected glass formulations and identify operational issues. Full-scale testing has provided critical design verification of the ICV™ process before operating the Hanford pilot-plant. In 2007, the project’s fifth full-scale test, called FS-38D, (also known as the Integrated Dryer Melter Test, or IDMT,) was performed. This test had three primary objectives: 1) Demonstrate the simultaneous and integrated operation of the ICV™ melter with a 10,000-liter dryer, 2) Demonstrate the effectiveness of a new feed reformulation and change in process methodology towards reducing the production and migration of molten ionic salts (MIS), and, 3) Demonstrate that an acceptable glass product is produced under these conditions. Testing was performed from August 8 to 17, 2007. Process and analytical results demonstrated that the primary test objectives, along with a dozen supporting objectives, were successfully met. Glass performance exceeded all disposal performance criteria. A previous issue with MIS containment was successfully resolved in FS-38D, and the ICV™ melter was integrated with a full-scale, 10,000-liter dryer. This paper describes the rationale for performing the test, the purpose and outcome of scale-up tests preceding it, and the performance and outcome of FS-38D.

  2. Hanford's Supplemental Treatment Project: Full-Scale Integrated Testing of In-Container-Vitrification and a 10,000-Liter Dryer

    SciTech Connect (OSTI)

    Witwer, K.S.; Dysland, E.J.; Garfield, J.S.; Beck, T.H.; Matyas, J.; Bagaasen, L.M.; Cooley, S.K.; Pierce, E.; Kim, D.S.; Schweiger, M.J.

    2008-07-01

    The GeoMelt{sup R} In-Container Vitrification{sup TM} (ICV{sup TM}) process was selected by the U.S. Department of Energy (DOE) in 2004 for further evaluation as the supplemental treatment technology for Hanford's low-activity waste (LAW). Also referred to as 'bulk vitrification', this process combines glass forming minerals, LAW, and chemical amendments; dries the mixture; and then vitrifies the material in a refractory-lined steel container. AMEC Nuclear Ltd. (AMEC) is adapting its GeoMelt ICV{sup TM} technology for this application with technical and analytical support from Pacific Northwest National Laboratory (PNNL). The DVBS project is funded by the DOE Office of River Protection and administered by CH2M HILL Hanford Group, Inc. The Demonstration Bulk Vitrification Project (DBVS) was initiated to engineer, construct, and operate a full-scale bulk vitrification pilot-plant to treat up to 750,000 liters of LAW from Waste Tank 241-S-109 at the DOE Hanford Site. Since the beginning of the DBVS project in 2004, testing has used laboratory, crucible-scale, and engineering-scale equipment to help establish process limitations of selected glass formulations and identify operational issues. Full-scale testing has provided critical design verification of the ICV{sup TM} process before operating the Hanford pilot-plant. In 2007, the project's fifth full-scale test, called FS-38D, (also known as the Integrated Dryer Melter Test, or IDMT,) was performed. This test had three primary objectives: 1) Demonstrate the simultaneous and integrated operation of the ICV{sup TM} melter with a 10,000- liter dryer, 2) Demonstrate the effectiveness of a new feed reformulation and change in process methodology towards reducing the production and migration of molten ionic salts (MIS), and, 3) Demonstrate that an acceptable glass product is produced under these conditions. Testing was performed from August 8 to 17, 2007. Process and analytical results demonstrated that the primary test objectives, along with a dozen supporting objectives, were successfully met. Glass performance exceeded all disposal performance criteria. A previous issue with MIS containment was successfully resolved in FS-38D, and the ICV{sup TM} melter was integrated with a full-scale, 10,000-liter dryer. This paper describes the rationale for performing the test, the purpose and outcome of scale-up tests preceding it, and the performance and outcome of FS-38D. (authors)

  3. Approaches To Integrating A HIgh Penertration Of Solar PV and CPV Onto The Electrical Grid

    E-Print Network [OSTI]

    Hill, Steven Craig

    2013-01-01

    in contacting staff of the Waste Water Treatment plant incapable of installation on waste water treatment plant (WWT)28   Waste Water Treatment 

  4. Radioactive Waste Management Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1999-07-09

    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.

  5. Technical area status report for low-level mixed waste final waste forms. Volume 2, Appendices

    SciTech Connect (OSTI)

    Mayberry, J.L.; Huebner, T.L. [Science Applications International Corp., Idaho Falls, ID (United States); Ross, W. [Pacific Northwest Lab., Richland, WA (United States); Nakaoka, R. [Los Alamos National Lab., NM (United States); Schumacher, R. [Westinghouse Savannah River Co., Aiken, SC (United States); Cunnane, J.; Singh, D. [Argonne National Lab., IL (United States); Darnell, R. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Greenhalgh, W. [Westinghouse Hanford Co., Richland, WA (United States)

    1993-08-01

    This report presents information on low-level mixed waste forms.The descriptions of the low-level mixed waste (LLMW) streams that are considered by the Mixed Waste Integrated Program (MWIP) are given in Appendix A. This information was taken from descriptions generated by the Mixed Waste Treatment Program (MWTP). Appendix B provides a list of characteristic properties initially considered by the Final Waste Form (FWF) Working Group (WG). A description of facilities available to test the various FWFs discussed in Volume I of DOE/MWIP-3 are given in Appendix C. Appendix D provides a summary of numerous articles that were reviewed on testing of FWFS. Information that was collected by the tests on the characteristic properties considered in this report are documented in Appendix D. The articles reviewed are not a comprehensive list, but are provided to give an indication of the data that are available.

  6. 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)

    2013-07-01

    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)

  7. WASTEWATER TREATMENT IN THE OIL SHALE INDUSTRY

    E-Print Network [OSTI]

    Fox, J.P.

    2010-01-01

    H. H. Peters, Shale Oil Waste Water Recovery by Evaporation,treatment of oil shale waste products. Consequently, bothmost difficult and costly oil shale waste stream requiring

  8. Vitrification of IFR and MSBR halide salt reprocessing wastes

    SciTech Connect (OSTI)

    Siemer, D.D.

    2013-07-01

    Both of the genuinely sustainable (breeder) nuclear fuel cycles (IFR - Integral Fast Reactor - and MSBR - Molten Salt Breeder Reactor -) studied by the USA's national laboratories would generate high level reprocessing waste (HLRW) streams consisting of a relatively small amount ( about 4 mole %) of fission product halide (chloride or fluoride) salts in a matrix comprised primarily (about 95 mole %) of non radioactive alkali metal halide salts. Because leach resistant glasses cannot accommodate much of any of the halides, most of the treatment scenarios previously envisioned for such HLRW have assumed a monolithic waste form comprised of a synthetic analog of an insoluble crystalline halide mineral. In practice, this translates to making a 'substituted' sodalite ('Ceramic Waste Form') of the IFR's chloride salt-based wastes and fluoroapatite of the MSBR's fluoride salt-based wastes. This paper discusses my experimental studies of an alternative waste management scenario for both fuel cycles that would separate/recycle the waste's halide and immobilize everything else in iron phosphate (Fe-P) glass. It will describe both how the work was done and what its results indicate about how a treatment process for both of those wastes should be implemented (fluoride and chloride behave differently). In either case, this scenario's primary advantages include much higher waste loadings, much lower overall cost, and the generation of a product (glass) that is more consistent with current waste management practices. (author)

  9. Solid low-level radioactive waste radiation stability studies 

    E-Print Network [OSTI]

    Williams, Arnold Andre?

    1989-01-01

    MANAGEMENT . . . Historical background Characteristics of radioactive wastes Classification of radioactive wastes Disposal methodology and criteria Handling and storage of radioactive wastes SOLID RADIOACTIVE WASTES Historical background... Characteristics of the solidified wastes Storage and handling of solid radioactive wastes Shipment of solid radioactive wastes Solidification of waste solutions MATERIALS AND METHODS Ion-exchange methods. High integrity containers (HIC). . tv tx 15 15...

  10. Integrated Closure and Monitoring Plan for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site

    SciTech Connect (OSTI)

    S. E. Rawlinson

    2001-09-01

    Bechtel Nevada (BN) manages two low-level Radioactive Waste Management Sites (RWMSs) (one site is in Area 3 and the other is in Area 5) at the Nevada Test Site (NTS) for the U.S. Department of Energy's (DOE's) National Nuclear Security Administration Nevada Operations Office (NNSA/NV). The current DOE Order governing management of radioactive waste is 435.1. Associated with DOE Order 435.1 is a Manual (DOE M 435.1-1) and Guidance (DOE G 435.1-1). The Manual and Guidance specify that preliminary closure and monitoring plans for a low-level waste (LLW) management facility be developed and initially submitted with the Performance Assessment (PA) and Composite Analysis (CA) for that facility. The Manual and Guidance, and the Disposal Authorization Statement (DAS) issued for the Area 3 RWMS further specify that the preliminary closure and monitoring plans be updated within one year following issuance of a DAS. This Integrated Closure and Monitoring Plan (ICMP) fulfills both requirements. Additional updates will be conducted every third year hereafter. This document is an integrated plan for closing and monitoring both RWMSs, and is based on guidance issued in 1999 by the DOE for developing closure plans. The plan does not follow the format suggested by the DOE guidance in order to better accommodate differences between the two RWMSs, especially in terms of operations and site characteristics. The modification reduces redundancy and provides a smoother progression of the discussion. The closure and monitoring plans were integrated because much of the information that would be included in individual plans is the same, and integration provides efficient presentation and program management. The ICMP identifies the regulatory requirements, describes the disposal sites and the physical environment where they are located, and defines the approach and schedule for both closing and monitoring the sites.

  11. Management of hazardous medical waste in Croatia

    SciTech Connect (OSTI)

    Marinkovic, Natalija Vitale, Ksenija; Holcer, Natasa Janev; Dzakula, Aleksandar; Pavic, Tomo

    2008-07-01

    This article provides a review of hazardous medical waste production and its management in Croatia. Even though Croatian regulations define all steps in the waste management chain, implementation of those steps is one of the country's greatest issues. Improper practice is evident from the point of waste production to final disposal. The biggest producers of hazardous medical waste are hospitals that do not implement existing legislation, due to the lack of education and funds. Information on quantities, type and flow of medical waste are inadequate, as is sanitary control. We propose an integrated approach to medical waste management based on a hierarchical structure from the point of generation to its disposal. Priority is given to the reduction of the amounts and potential for harm. Where this is not possible, management includes reduction by sorting and separating, pretreatment on site, safe transportation, final treatment and sanitary disposal. Preferred methods should be the least harmful for human health and the environment. Integrated medical waste management could greatly reduce quantities and consequently financial strains. Landfilling is the predominant route of disposal in Croatia, although the authors believe that incineration is the most appropriate method. In a country such as Croatia, a number of small incinerators would be the most economical solution.

  12. Fate of As, Se, and Hg in a Passive Integrated System for Treatment of Fossil Plant Wastewater

    SciTech Connect (OSTI)

    Terry Yost; Paul Pier; Gregory Brodie

    2007-12-31

    TVA is collaborating with EPRI and DOE to demonstrate a passive treatment system for removing SCR-derived ammonia and trace elements from a coal-fired power plant wastewater stream. The components of the integrated system consist of trickling filters for ammonia oxidation, reaction cells containing zero-valent iron (ZVI) for trace contaminant removal, a settling basin for storage of iron hydroxide floc, and anaerobic vertical-flow wetlands for biological denitrification. The passive integrated treatment system will treat up to 0.25 million gallons per day (gpd) of flue gas desulfurization (FGD) pond effluent, with a configuration requiring only gravity flow to obviate the need for pumps. The design of the system will enable a comparative evaluation of two parallel treatment trains, with and without the ZVI extraction trench and settling/oxidation basin components. One of the main objectives is to gain a better understanding of the chemical transformations that species of trace elements such as arsenic, selenium, and mercury undergo as they are treated in passive treatment system components with differing environmental conditions. This progress report details the design criteria for the passive integrated system for treating fossil power plant wastewater as well as performance results from the first several months of operation. Engineering work on the project has been completed, and construction took place during the summer of 2005. Monitoring of the passive treatment system was initiated in October 2005 and continued until May 18 2006. The results to date indicate that the treatment system is effective in reducing levels of nitrogen compounds and trace metals. Concentrations of both ammonia and trace metals were lower than expected in the influent FGD water, and additions to increase these concentrations will be done in the future to further test the removal efficiency of the treatment system. In May 2006, the wetland cells were drained of FGD water, refilled with less toxic ash pond water, and replanted due to low survival rates from the first planting the previous summer. The goals of the TVA-EPRI-DOE collaboration include building a better understanding of the chemical transformations that trace elements such as arsenic, selenium, and mercury undergo as they are treated in a passive treatment system, and to evaluate the performance of a large-scale replicated passive treatment system to provide additional design criteria and economic factors.

  13. 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.; Bickford, D.F.; Cicero, C.A.

    1995-01-25

    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.

  14. Large-Scale Testing of Effects of Anti-Foam Agent on Gas Holdup in Process Vessels in the Hanford Waste Treatment Plant - 8280

    SciTech Connect (OSTI)

    Mahoney, Lenna A.; Alzheimer, James M.; Arm, Stuart T.; Guzman-Leong, Consuelo E.; Jagoda, Lynette K.; Stewart, Charles W.; Wells, Beric E.; Yokuda, Satoru T.

    2008-06-03

    The Hanford Waste Treatment Plant (WTP) will vitrify the radioactive wastes stored in underground tanks. These wastes generate and retain hydrogen and other flammable gases that create safety concerns for the vitrification process tanks in the WTP. An anti-foam agent (AFA) will be added to the WTP process streams. Prior testing in a bubble column and a small-scale impeller-mixed vessel indicated that gas holdup in a high-level waste chemical simulant with AFA was up to 10 times that in clay simulant without AFA. This raised a concern that major modifications to the WTP design or qualification of an alternative AFA might be required to satisfy plant safety criteria. However, because the mixing and gas generation mechanisms in the small-scale tests differed from those expected in WTP process vessels, additional tests were performed in a large-scale prototypic mixing system with in situ gas generation. This paper presents the results of this test program. The tests were conducted at Pacific Northwest National Laboratory in a Ľ-scale model of the lag storage process vessel using pulse jet mixers and air spargers. Holdup and release of gas bubbles generated by hydrogen peroxide decomposition were evaluated in waste simulants containing an AFA over a range of Bingham yield stresses and gas gen geration rates. Results from the Ľ-scale test stand showed that, contrary to the small-scale impeller-mixed tests, gas holdup in clay without AFA is comparable to that in the chemical waste simulant with AFA. The test stand, simulants, scaling and data-analysis methods, and results are described in relation to previous tests and anticipated WTP operating conditions.

  15. Large-Scale Testing of Effects of Anti-Foam Agent on Gas Holdup in Process Vessels in the Hanford Waste Treatment Plant

    SciTech Connect (OSTI)

    Mahoney, L.A.; Alzheimer, J.M.; Arm, S.T.; Guzman-Leong, C.E.; Jagoda, L.K.; Stewart, C.W.; Wells, B.E.; Yokuda, S.T. [Pacific Northwest National Laboratory, Richland, WA (United States)

    2008-07-01

    The Hanford Waste Treatment and Immobilization Plant (WTP) will vitrify the radioactive wastes stored in underground tanks. These wastes generate and retain hydrogen and other flammable gases that create safety concerns for the vitrification process tanks in the WTP. An anti-foam agent (AFA) will be added to the WTP process streams. Previous testing in a bubble column and a small-scale impeller-mixed vessel indicated that gas holdup in a high-level waste chemical simulant with AFA was as much as 10 times higher than in clay simulant without AFA. This raised a concern that major modifications to the WTP design or qualification of an alternative AFA might be required to satisfy plant safety criteria. However, because the mixing and gas generation mechanisms in the small-scale tests differed from those expected in WTP process vessels, additional tests were performed in a large-scale prototypic mixing system with in situ gas generation. This paper presents the results of this test program. The tests were conducted at Pacific Northwest National Laboratory in a 1/4-scale model of the lag storage process vessel using pulse jet mixers and air spargers. Holdup and release of gas bubbles generated by hydrogen peroxide decomposition were evaluated in waste simulants containing an AFA over a range of Bingham yield stresses and gas generation rates. Results from the 1/4-scale test stand showed that, contrary to the small-scale impeller-mixed tests, holdup in the chemical waste simulant with AFA was not so greatly increased compared to gas holdup in clay without AFA. The test stand, simulants, scaling and data-analysis methods, and results are described in relation to previous tests and anticipated WTP operating conditions. (authors)

  16. 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.

    2010-08-12

    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.

  17. 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.

    2011-07-14

    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.

  18. Semi-analytic treatment of nearly-singular Galerkin surface integrals

    SciTech Connect (OSTI)

    Nintcheu Fata, Sylvain

    2010-01-01

    On utilizing piecewise linear test and interpolation functions over flat triangles, three semi-analytic techniques for evaluating nearly-singular surface integrals of potential theory are developed and investigated in the context of a three-dimensional Galerkin approximation. In all procedures, the inner surface integral is calculated exactly via recursive expressions defined over the edges of the integration triangle. In addition, the proposed methods respectively employ a Duffy transformation, sinh transformations, and polynomial transformations to weaken or smooth out near singularities, followed by a standard product Gauss-Legendre quadrature rule to compute the outer boundary integral. Numerical experiments and comparisons of the proposed approaches are included to provide more insight into the performance of these techniques. Computational tests have demonstrated that the algorithm based on a Duffy transformation is the most efficient and effective method for dealing with nearly-singular as well as well-separated integrals.

  19. Characterization, Monitoring, and Sensor Technology Integrated Program (CMST-IP). Technology summary

    SciTech Connect (OSTI)

    Not Available

    1994-04-01

    The Characterization, Monitoring, and Sensor Technology Integrated Program seeks to deliver needed technologies, timely and cost-effectively, to the Office of Waste Management (EM-30), the Office of Environmental Restoration (EM-40), and the Office of Facility Transition and Management (EM-60). The scope of characterizations monitoring, and sensor technology needs that are required by those organizations encompass: (1) initial location and characterization of wastes and waste environments - prior to treatment; (2) monitoring of waste retrieval, remediation and treatment processes; (3) characterization of the co-position of final waste treatment forms to evaluate the performance of waste treatments processes; and (4) site closure and compliance monitoring. Wherever possible, the CMST-IP fosters technology transfer and commercialization of technologies that it sponsors.

  20. Annual summary of Immobilized Low-Activity Waste (ILAW) Performance Assessment for 2003 Incorporating the Integrated Disposal Facility Concept

    SciTech Connect (OSTI)

    MANN, F M

    2003-09-01

    To Erik Olds 09/30/03 - An annual summary of the adequacy of the Hanford Immobilized Low-Activity Tank Waste Performance Assessment (ILAW PA) is necessary in each year in which a full performance assessment is not issued.