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Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
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1

Process for preparing liquid wastes  

DOE Patents [OSTI]

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

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

1997-01-01T23:59:59.000Z

2

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

E-Print Network [OSTI]

waste (i.e, mixture of biohazardous and chemical or radioactive waste), call Environment, Health2/2009 Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste Description Biohazard symbol Address: UCSD 200 West Arbor Dr. San Diego, CA 92103 (619

Tsien, Roger Y.

3

SRS - Programs - Liquid Waste Disposition  

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

Liquid Waste Disposition Liquid Waste Disposition This includes both the solidification of highly radioactive liquid wastes stored in SRS's tank farms and disposal of liquid low-level waste generated as a by-product of the separations process and tank farm operations. This low-level waste is treated in the Effluent Treatment Facility. High-activity liquid waste is generated at SRS as by-products from the processing of nuclear materials for national defense, research and medical programs. The waste, totaling about 36 million gallons, is currently stored in 49 underground carbon-steel waste tanks grouped into two "tank farms" at SRS. While the waste is stored in the tanks, it separates into two parts: a sludge that settles on the bottom of the tank, and a liquid supernate that resides on top of the sludge. The waste is reduced to about 30 percent of its original volume by evaporation. The condensed evaporator "overheads" are transferred to the Effluent Treatment Project for final cleanup prior to release to the environment. As the concentrate cools a portion of it crystallizes forming solid saltcake. The concentrated supernate and saltcake are less mobile and therefore less likely to escape to the environment in the event of a tank crack or leak.

4

DOE Selects Savannah River Remediation, LLC for Liquid Waste...  

Energy Savers [EERE]

objective of the Liquid Waste contract is to achieve closure of the SRS liquid waste tanks in compliance with the Federal Facilities Agreement, utilizing the Defense Waste...

5

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

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

far will integrate SWPF with current liquid waste facilities, such as the DWPF and the tanks farms." EM is pleased with the spirit of integration. "A key objective for us over the...

6

SRS Liquid Waste Program Partnering Agreement  

Broader source: Energy.gov [DOE]

We the members of the SRS Liquid Waste Partnering Team do hereby mutually agree to work in a collaborative and cooperative manner through open communication and coordination with team members, and...

7

Deployment of Performance Management Methodology as part of Liquid Waste Program at Savannah River Site - 12178  

SciTech Connect (OSTI)

In 2009, Savannah River Remediation LLC (SRR) assumed the management lead of the Liquid Waste (LW) Program at the Savannah River Site (SRS). The four SRR partners and AREVA, as an integrated subcontractor are performing the ongoing effort to safely and reliably: - Close High Level Waste (HLW) storage tanks; - Maximize waste throughput at the Defense Waste Processing Facility (DWPF); - Process salt waste into stable final waste form; - Manage the HLW liquid waste material stored at SRS. As part of these initiatives, SRR and AREVA deployed a performance management methodology based on Overall Equipment Effectiveness (OEE) at the DWPF in order to support the required production increase. This project took advantage of lessons learned by AREVA through the deployment of Total Productive Maintenance and Visual Management methodologies at the La Hague reprocessing facility in France. The project also took advantage of measurement data collected from different steps of the DWPF process by the SRR team (Melter Engineering, Chemical Process Engineering, Laboratory Operations, Plant Operations). Today the SRR team has a standard method for measuring processing time throughout the facility, a reliable source of objective data for use in decision-making at all levels, and a better balance between engineering department goals and operational goals. Preliminary results show that the deployment of this performance management methodology to the LW program at SRS has already significantly contributed to the DWPF throughput increases and is being deployed in the Saltstone facility. As part of the liquid waste program on Savannah River Site, SRR committed to enhance production throughput of DWPF. Beyond technical modifications implemented at different location of the facility, SRR deployed performance management methodology based on OEE metrics. The implementation benefited from the experience gained by AREVA in its own facilities in France. OEE proved to be a valuable tool in order to support the enhancement program in DWPF by providing unified metrics to measure plant performances, identify bottleneck location, and rank the most time consuming causes from objective data shared between the different groups belonging to the organization. Beyond OEE, the Visual Management tool adapted from the one used at La Hague were also provided in order to further enhance communication within the operating teams. As a result of all the initiatives implemented on DWPF, achieved production has been increased to record rates from FY10 to FY11. It is expected that thanks to the performance management tools now available within DWPF, these results will be sustained and even improved in the future to meet system plan targets. (authors)

Prod'homme, A.; Drouvot, O.; Gregory, J. [AREVA, Paris (France); Barnes, B.; Hodges, B.; Hart, M. [SRR, Aiken, SC (United States)

2012-07-01T23:59:59.000Z

8

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

Office of Environmental Management (EM)

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

9

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

Office of Environmental Management (EM)

now been filled. The SDUs play an essential role in the closure of the 45 liquid waste tanks on the site. About 90 percent of the waste in these tanks is salt waste that must be...

10

Ventilation System to Improve Savannah River Site's Liquid Waste Operations  

Broader source: Energy.gov [DOE]

AIKEN, S.C. The EM program and its liquid waste contractor at the Savannah River Site are improving salt waste disposition work and preparing for eventual operations of the Salt Waste Processing Facility (SWPF) currently being constructed.

11

Existing data on the 216-Z liquid waste sites  

SciTech Connect (OSTI)

During 36 years of operation at the Hanford Site, the ground has been used for disposal of liquid and solid transuranic and/or low-level wastes. Liquid waste was disposed in surface and subsurface cribs, trenches, French drains, reverse wells, ditches and ponds. Disposal structures associated with Z Plant received liquid waste from plutonium finishing and reclamation, waste treatment and laboratory operations. The nineteen 216-Z sites have received 83% of the plutonium discharged to 325 liquid waste facilities at the Hanford Site. The purpose of this document is to support the Hanford Defense Waste Environmental Impact Statement by drawing the existing data together for the 216-Z liquid waste disposal sites. This document provides an interim reference while a sitewide Waste Information Data System (WIDS) is developed and put on line. Eventually these and additional site data for all Hanford waste disposal sites will be available on WIDS. Compilation of existing data is the first step in evaluating the need and developing the technology for long-term management of these waste sites. The scope of this document is confined to data describing the status of the 216-Z waste sites as of December 31, 1979. Information and sketches are taken from existing documents and drawings.

Owens, K.W.

1981-05-01T23:59:59.000Z

12

High-Level Liquid Waste Tank Integrity Workshop - 2008  

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

Liquid Waste Tank Integrity Liquid Waste Tank Integrity Workshop - 2008 Karthik Subramanian Bruce Wiersma November 2008 High Level Waste Corporate Board Meeting karthik.subramanian@srnl.doe.gov bruce.wiersma@srnl.doe.gov 2 Acknowledgements * Bruce Wiersma (SRNL) * Kayle Boomer (Hanford) * Michael T. Terry (Facilitator) * SRS - Liquid Waste Organization * Hanford Tank Farms * DOE-EM 3 Background * High level radioactive waste (HLW) tanks provide critical interim confinement for waste prior to processing and permanent disposal * Maintaining structural integrity (SI) of the tanks is a critical component of operations 4 Tank Integrity Workshop - 2008 * Discuss the HLW tank integrity technology needs based upon the evolving waste processing and tank closure requirements along with its continued storage mission

13

Detection of free liquid in containers of solidified radioactive waste  

DOE Patents [OSTI]

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

Greenhalgh, Wilbur O. (Richland, WA)

1985-01-01T23:59:59.000Z

14

Elimination of liquid discharge to the environment from the TA-50 Radioactive Liquid Waste Treatment Facility  

SciTech Connect (OSTI)

Alternatives were evaluated for management of treated radioactive liquid waste from the radioactive liquid waste treatment facility (RLWTF) at Los Alamos National Laboratory. The alternatives included continued discharge into Mortandad Canyon, diversion to the sanitary wastewater treatment facility and discharge of its effluent to Sandia Canyon or Canada del Buey, and zero liquid discharge. Implementation of a zero liquid discharge system is recommended in addition to two phases of upgrades currently under way. Three additional phases of upgrades to the present radioactive liquid waste system are proposed to accomplish zero liquid discharge. The first phase involves minimization of liquid waste generation, along with improved characterization and monitoring of the remaining liquid waste. The second phase removes dissolved salts from the reverse osmosis concentrate stream to yield a higher effluent quality. In the final phase, the high-quality effluent is reused for industrial purposes within the Laboratory or evaporated. Completion of these three phases will result in zero discharge of treated radioactive liquid wastewater from the RLWTF.

Moss, D.; Williams, N.; Hall, D.; Hargis, K.; Saladen, M.; Sanders, M.; Voit, S.; Worland, P.; Yarbro, S.

1998-06-01T23:59:59.000Z

15

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

Broader source: Energy.gov [DOE]

AIKEN, S.C. Officials with the EM program at Savannah River Site (SRS) recently announced a key milestone in preparation for the startup of the Salt Waste Processing Facility (SWPF): workers installed more than 1,200 feet of new transfer lines that will eventually connect existing liquid waste facilities to SWPF.

16

China's Scientific Investigation for Liquid Waste Treatment Solutions  

SciTech Connect (OSTI)

Post World War II created the nuclear age with several countries developing nuclear technology for power, defense, space and medical applications. China began its nuclear research and development programs in 1950 with the establishment of the China Institute of Atomic Energy (CIAE) located near Beijing. CIAE has been China's leader in nuclear science and technical development with its efforts to create advanced reactor technology and upgrade reprocessing technology. In addition, with China's new emphasis on environmental safety, CIAE is focusing on waste treatment options and new technologies that may provide solutions to legacy waste and newly generated waste from the full nuclear cycle. Radioactive liquid waste can pose significant challenges for clean up with various treatment options including encapsulation (cement), vitrification, solidification and incineration. Most, if not all, nuclear nations have found the treatment of liquids to be difficult, due in large part to the high economic costs associated with treatment and disposal and the failure of some methods to safely contain or eliminate the liquid. With new environmental regulations in place, Chinese nuclear institutes and waste generators are beginning to seek new technologies that can be used to treat the more complex liquid waste streams in a form that is safe for transport and for long-term storage or final disposal. [1] In 2004, CIAE and Pacific Nuclear Solutions, a division of Pacific World Trade, USA, began discussions about absorbent technology and applications for its use. Preliminary tests were conducted at CIAE's Department of Radiochemistry using generic solutions, such as lubricating oil, with absorbent polymers for solidification. Based on further discussions between both parties, it was decided to proceed with a more formal test program in April, 2005, and additional tests in October, 2005. The overall objective of the test program was to apply absorbent polymers to various waste streams to determine leach rates, stability (immobilization), effective bonding ratios, compression capability, waste minimization and effects of irradiation on the solidified samples. (authors)

Liangjin, B.; Meiqiong, L. [China Institute of Atomic Energy, P.O. Box 275(87), Beijing, 102413 (China); Kelley, D. [Pacific Nuclear Solutions, 450 East 96th Street, Suite 335, Indianapolis, Indiana 46240 (United States)

2006-07-01T23:59:59.000Z

17

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

SciTech Connect (OSTI)

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

COZZI, ALEX

2004-02-18T23:59:59.000Z

18

Process for immobilizing radioactive boric acid liquid wastes  

DOE Patents [OSTI]

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

Greenhalgh, Wilbur O. (Richland, WA)

1986-01-01T23:59:59.000Z

19

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

Broader source: Energy.gov [DOE]

Municipal solid waste (MSW) is a domestic energy resource with the potential to provide a significant amount of energy to meet US liquid fuel requirements. MSW is defined as household waste, commercial solid waste, nonhazardous sludge, conditionally exempt, small quantity hazardous waste, and industrial solid waste. It includes food waste, residential rubbish, commercial and industrial wastes, and construction and demolition debris. It has an average higher heating value (HHV) of approximately 5100 btu/lb (as arrived basis).

20

An evaluation of neutralization for processing sodium-bearing liquid waste  

SciTech Connect (OSTI)

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

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

1989-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Enclosure 3 DOE Response to EPA Question Regarding "High-Level Liquid Radioactive Waste"  

E-Print Network [OSTI]

to date, which is from the definitions in the Nuclear Waste Policy Act: The term "high-level radioactive of waste streams as from the applicable definition of HLW in the Nuclear Waste Policy Act. 5/11/20051 #12 defining High Level Waste: For the purpose of this statement of policy, "high-level liquid radioactive

22

The Savannah River Site's liquid radioactive waste operations involves the man  

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

Site's liquid radioactive waste operations involves the management of space in the Site's Site's liquid radioactive waste operations involves the management of space in the Site's 49 underground waste tanks, including the removal of waste materials. Once water is removed from the waste tanks, two materials remain: salt and sludge waste. Removing salt waste, which fills approximately 90 percent of the tank space in the SRS tank farms, is a major step toward closing the Site's waste tanks that currently contain approximately 38 million gallons of waste. Due to the limited amount of tank space available in new-style tanks, some salt waste must be dispositioned in the interim to ensure sufficient tank space for continued sludge washing and to support the initial start-up and salt processing operations at the Salt Waste Processing Facility (SWPF).

23

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

Broader source: Energy.gov [DOE]

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

24

Liquid and gaseous waste operations section. Annual operating report CY 1997  

SciTech Connect (OSTI)

This document presents information on the liquid and gaseous wastes operations section for calendar year 1997. Operating activities, upgrade activities, and maintenance activities are described.

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

1998-03-01T23:59:59.000Z

25

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

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

Radioactive Liquid Waste Radioactive Liquid Waste Treatment Facility Replacement Project at Los Alamos National Laboratory OAS-L-13-15 September 2013 Department of Energy Washington, DC 20585 September 26, 2013 MEMORANDUM FOR THE ASSOCIATE ADMINISTRATOR FOR ACQUISITION AND PROJECT MANAGEMENT MANAGER LOS ALAMOS FIELD OFFICE FROM: David Sedillo Western Audits Division Office of Inspector General SUBJECT: INFORMATION: Audit Report on "The Radioactive Liquid Waste Treatment Facility Replacement Project at Los Alamos National Laboratory" BACKGROUND The Department of Energy's Los Alamos National Laboratory (Los Alamos) is a Government- owned, contractor operated Laboratory that is part of the National Nuclear Security Administration's (NNSA) nuclear weapons complex. Los Alamos' primary responsibility is to

26

MEMORANDUM TO: FILE Dt Lw;v,e  

Office of Legacy Management (LM)

Dt Dt Lw;v,e t=ROM: ---------------- SUBJECT: G( ;Vd ;fi&-i0In @BCWbVjCAI\&=t& DATE 5--$$b7 ---- mm ---------- SITE NAME: JhzA-~~ c5b+vw (-t-~~~~~~~~-~-~-~~~~~~~~~-------------------- -------------------- CITY: &tiu$r 3uc&l/\ STATE: co ---------------------m-me- ------ OWNER(S) -------- Past:-------_-_______________ Current: --mmmm--m-w--------------- Owner contacted 0 yes egno; if yes, date contacted ------------- TYPE OF OPERATION ----------------- 0 Research P Development 0 Facility Type 0 Production scale testing 0 Pilot Scale 0 Manufacturing 0 Bench Scale Process 0 University 0 Theoretical Studies a Research Organization a 0 Government Sponsored Facility Sample s( Analysis %Tf$ 0 Other --------------------- j3 Production

27

DOE Selects Savannah River Remediation, LLC for Liquid Waste Contract at  

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

DOE Selects Savannah River Remediation, LLC for Liquid Waste DOE Selects Savannah River Remediation, LLC for Liquid Waste Contract at Savannah River Site DOE Selects Savannah River Remediation, LLC for Liquid Waste Contract at Savannah River Site December 8, 2008 - 4:58pm Addthis Washington, D.C. -The U.S. Department of Energy (DOE) today announced the award to Savannah River Remediation, LLC as the liquid waste contractor for DOE's Savannah River Site (SRS) in Aiken, South Carolina. The contract is a cost-plus award-fee contract valued at approximately $3.3 billion over the entire contract, consisting of a base period of six years, plus an option to extend for up to two additional years. The base performance period of the contract will be from April 1, 2009 through March 31, 2015. A 90-day transition period will begin January 2, 2009.

28

DOE Selects Savannah River Remediation, LLC for Liquid Waste Contract at  

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

DOE Selects Savannah River Remediation, LLC for Liquid Waste DOE Selects Savannah River Remediation, LLC for Liquid Waste Contract at Savannah River Site DOE Selects Savannah River Remediation, LLC for Liquid Waste Contract at Savannah River Site December 8, 2008 - 4:58pm Addthis Washington, D.C. -The U.S. Department of Energy (DOE) today announced the award to Savannah River Remediation, LLC as the liquid waste contractor for DOE's Savannah River Site (SRS) in Aiken, South Carolina. The contract is a cost-plus award-fee contract valued at approximately $3.3 billion over the entire contract, consisting of a base period of six years, plus an option to extend for up to two additional years. The base performance period of the contract will be from April 1, 2009 through March 31, 2015. A 90-day transition period will begin January 2, 2009.

29

Thermal treatment of historical radioactive solid and liquid waste into the CILVA incinerator  

SciTech Connect (OSTI)

Since the very beginning of the nuclear activities in Belgium, the incineration of radioactive waste was chosen as a suitable technique for achieving an optimal volume reduction of the produced waste quantities. Based on the 35 years experience gained by the operation of the old incinerator, a new industrial incineration plant started nuclear operation in May 1995, as a part of the Belgian Centralized Treatment/Conditioning Facility named CILVA. Up to the end of 2006, the CILVA incinerator has burnt 1660 tonne of solid waste and 419 tonne of liquid waste. This paper describes the type and allowable radioactivity of the waste, the incineration process, heat recovery and the air pollution control devices. Special attention is given to the treatment of several hundreds of tonne historical waste from former reprocessing activities such as alpha suspected solid waste, aqueous and organic liquid waste and spent ion exchange resins. The capacity, volume reduction, chemical and radiological emissions are also evaluated. BELGOPROCESS, a company set up in 1984 at Dessel (Belgium) where a number of nuclear facilities were already installed is specialized in the processing of radioactive waste. It is a subsidiary of ONDRAF/NIRAS, the Belgian Nuclear Waste Management Agency. According to its mission statement, the activities of BELGOPROCESS focus on three areas: treatment, conditioning and interim storage of radioactive waste; decommissioning of shut-down nuclear facilities and cleaning of contaminated buildings and land; operating of storage sites for conditioned radioactive waste. (authors)

Deckers, Jan; Mols, Ludo [Belgoprocess NV, Operations Department, Gravenstraat 73, B-2480 Dessel (Belgium)

2007-07-01T23:59:59.000Z

30

Radioactive Liquid Waste Treatment Facility Discharges in 2011  

SciTech Connect (OSTI)

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.

Del Signore, John C. [Los Alamos National Laboratory

2012-05-16T23:59:59.000Z

31

Biological Information Document, Radioactive Liquid Waste Treatment Facility  

SciTech Connect (OSTI)

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.

Biggs, J.

1995-12-31T23:59:59.000Z

32

System for removing liquid waste from a tank  

DOE Patents [OSTI]

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

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

1994-04-26T23:59:59.000Z

33

System for removing liquid waste from a tank  

DOE Patents [OSTI]

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

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

1994-01-01T23:59:59.000Z

34

Evaluation of System Level Modeling and Simulation Tools in Support of Savannah River Site Liquid Waste Process  

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

Savannah River Site Liquid Waste Process Savannah River Site Liquid Waste Process June 2009 Monica C. Regalbuto Office of Waste Processing DOE/EM Kevin G. Brown Vanderbilt University and CRESP David W. DePaoli Oak Ridge National Laboratory Candido Pereira Argonne National Laboratory John R. Shultz Office of Waste Processing DOE/EM Sahid C. Smith Office of Waste Processing DOE/EM External Technical Review for Evaluation of System Level Modeling and Simulation Tools in Support of Savannah River Site Liquid Waste Process June 2009 ACKNOWLEDGEMENTS The Review Team thanks Ms. Sonitza Blanco, Team Lead Planning and Coordination Waste Disposition Project U.S. Department of Energy Savannah River Operations Office and Mr. Pete Hill, Liquid Waste Planning Manager for Washington Savannah River Company, for their

35

Contact glow discharge electrolysis for liquid waste processing  

E-Print Network [OSTI]

for an alka- line water electrolysis at a small pin verticaldischarge electrolysis applied to waste water treatment.water treatment induced by plasma with contact glow discharge electrolysis.

Sharma, Neeraj

2014-01-01T23:59:59.000Z

36

PROBABILITY BASED CORROSION CONTROL FOR LIQUID WASTE TANKS - PART III  

SciTech Connect (OSTI)

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

Hoffman, E.; Edwards, T.

2010-12-09T23:59:59.000Z

37

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

SciTech Connect (OSTI)

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)

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

2013-07-01T23:59:59.000Z

38

Liquid and Gaseous Waste Operations Project Annual Operating Report CY 1999  

SciTech Connect (OSTI)

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

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

2000-03-01T23:59:59.000Z

39

US and Russian innovative technologies to process low-level liquid radioactive wastes: The Murmansk initiative  

SciTech Connect (OSTI)

This paper documents the status of the technical design for the upgrade and expansion to the existing Low-level Liquid Radioactive Waste (LLLRW) treatment facility in Murmansk, the Russian Federation. This facility, owned by the Ministry of Transportation and operated by the Russian company RTP Atomflot in Murmansk, Russia, has been used by the Murmansk Shipping Company (MSCo) to process low-level liquid radioactive waste generated by the operation of its civilian icebreaker fleet. The purpose of the new design is to enable Russia to permanently cease the disposal at sea of LLLRW in the Arctic, and to treat liquid waste and high saline solutions from both the Civil and North Navy Fleet operations and decommissioning activities. Innovative treatments are to be used in the plant which are discussed in this paper.

Dyer, R.S. [Environmental Protection Agency, Washington, DC (United States); Penzin, R. [Association for Advanced Technologies, Moscow (Russian Federation); Duffey, R.B. [Brookhaven National Lab., Upton, NY (United States); Sorlie, A. [Norwegian Radiation Protection Authority, Osteras (Norway)

1996-12-31T23:59:59.000Z

40

Role of Liquid Waste Pretreatment Technologies in Solving the DOE Clean-up Mission  

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

Role of Liquid Waste Pretreatment Technologies in Role of Liquid Waste Pretreatment Technologies in Solving the DOE Clean-up Mission W. R. Wilmarth March 5 2009 March 5, 2009 HLW Corporate Board Phoenix AZ HLW Corporate Board, Phoenix, AZ Co-authors M. E. Johnson, CH2M Hill Plateau Remediation Company G. Lumetta, Pacific Northwest National Laboratory N Machara DOE Office of Engineering and Technology N. Machara, DOE Office of Engineering and Technology M. R. Poirier, Savannah River National Laboratory P C S DOE S h Ri P. C. Suggs, DOE Savannah River M. C. Thompson, Savannah River National Laboratory, Retired Retired 2 Background Separations is a fundamental business within DOE. The role of separations today is to expedite waste retrieval The role of separations today is to expedite waste retrieval, processing and closure. Recognized as part of E&T Roadmap

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

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

SciTech Connect (OSTI)

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

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

1996-05-01T23:59:59.000Z

42

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

Energy Savers [EERE]

Synthesis, Volume 2: A Techno-economic Evaluation of the Production of Mixed Alcohols Biomass is a renewable energy resource that can be converted into liquid fuel suitable for...

43

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

SciTech Connect (OSTI)

Various forms of general and localized corrosion represent principal threats to the integrity of DOE liquid waste storage tanks. These tanks, which are of a single wall or double wall design, depending upon their age, are fabricated from welded carbon steel and contain a complex waste-form comprised of NaOH and NaNO3, along with trace amounts of phosphate, sulfate, carbonate, and chloride. Because waste leakage can have a profound environmental impact, considerable interest exists in predicting the accumulation of corrosion damage, so as to more effectively schedule maintenance and repair.

MacDonal, Digby D.; Marx, Brian M.; Ahn, Sejin; Ruiz, Julio de; Soundararajan, Balaji; Smith, Morgan; Coulson, Wendy

2005-06-15T23:59:59.000Z

44

Removal of Radioactive Nuclides from Mo-99 Acidic Liquid Waste - 13027  

SciTech Connect (OSTI)

About 200 liters highly radioactive acidic liquid waste originating from Mo-99 production was stored at INER (Institute of Nuclear Energy Research). A study regarding the treatment of the radioactive acidic liquid waste was conducted to solve storage-related issues and allow discharge of the waste while avoiding environmental pollution. Before discharging the liquid waste, the acidity, NO{sub 3}{sup -} and Hg ions in high concentrations, and radionuclides must comply with environmental regulations. Therefore, the treatment plan was to neutralize the acidic liquid waste, remove key radionuclides to reduce the dose rate, and then remove the nitrate and mercury ions. Bench tests revealed that NaOH is the preferred solution to neutralize the high acidic waste solution and the pH of solution must be adjusted to 9?11 prior to the removal of nuclides. Significant precipitation was produced when the pH of solution reached 9. NaNO{sub 3} was the major content in the precipitate and part of NaNO{sub 3} was too fine to be completely collected by filter paper with a pore size of approximately 3 ?m. The residual fine particles remaining in solution therefore blocked the adsorption column during operation. Two kinds of adsorbents were employed for Cs-137 and a third for Sr-90 removal to minimize cost. For personnel radiation protection, significant lead shielding was required at a number of points in the process. The final process design and treatment facilities successfully treated the waste solutions and allowed for environmentally compliant discharge. (authors)

Hsiao, Hsien-Ming; Pen, Ben-Li [Chemical Engineering Division, Institute of Nuclear Energy Research, P.O. Box 3-7, Longtan 32546 Taiwan, Republic of China (China)] [Chemical Engineering Division, Institute of Nuclear Energy Research, P.O. Box 3-7, Longtan 32546 Taiwan, Republic of China (China)

2013-07-01T23:59:59.000Z

45

ivestock and poultry operations frequently use anaerobic lagoons as liquid waste storage and  

E-Print Network [OSTI]

, The Texas A&M University System. #12;Pumping Pumping from the lagoon should be conducted annually, at least the designed life of sludge storage, frequent agitation and pumping may be necessary. In addition, solidsL ivestock and poultry operations frequently use anaerobic lagoons as liquid waste storage

Mukhtar, Saqib

46

External Technical Review for Evaluation of System Level Modeling and Simulation Tools in Support of Hanford Site Liquid Waste Process  

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

Hanford Site Liquid Waste Process Hanford Site Liquid Waste Process September 2009 Monica C. Regalbuto Office of Waste Processing DOE/EM Kevin G. Brown Vanderbilt University and CRESP David W. DePaoli Oak Ridge National Laboratory Candido Pereira Argonne National Laboratory John R. Shultz Office of Waste Processing DOE/EM External Technical Review for Evaluation of System Level Modeling and Simulation Tools in Support of Hanford Site Liquid Waste Process September 2009 Acknowledgements The Review Team thanks Mr. Glyn Trenchard, Team Lead for Planning and Coordination Waste Disposition Project, U.S. Department of Energy--Office of River Protection, Mr. Paul Rutland, RPP System Planning Manager for Washington River Protection Solutions, and Mr. Ernie Lee,

47

Treatment of Liquid Radioactive Waste with High Salt Content by Colloidal Adsorbents - 13274  

SciTech Connect (OSTI)

Treatment processes have been fully developed for most of the liquid radioactive wastes generated during the operation of nuclear power plants. However, a process for radioactive liquid waste with high salt content, such as waste seawater generated from the unexpected accident at nuclear power station, has not been studied extensively. In this study, the adsorption efficiencies of cesium (Cs) and strontium (Sr) in radioactive liquid waste with high salt content were investigated using several types of zeolite with different particle sizes. Synthesized and commercial zeolites were used for the treatment of simulated seawater containing Cs and Sr, and the reaction kinetics and adsorption capacities of colloidal zeolites were compared with those of bulk zeolites. The experimental results demonstrated that the colloidal adsorbents showed fast adsorption kinetic and high binding capacity for Cs and Sr. Also, the colloidal zeolites could be successfully applied to the static adsorption condition, therefore, an economical benefit might be expected in an actual processes where stirring is not achievable. (authors)

Lee, Keun-Young; Chung, Dong-Yong; Kim, Kwang-Wook; Lee, Eil-Hee; Moon, Jei-Kwon [Korea Atomic Energy Research Institute - KAERI, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)] [Korea Atomic Energy Research Institute - KAERI, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

2013-07-01T23:59:59.000Z

48

Savannah River Site, Liquid Waste Program, Savannah River Remediation American Recovery and Reinvestment Act Benefits and Lessons Learned - 12559  

SciTech Connect (OSTI)

Utilizing funding provided by the American Recovery and Reinvestment Act (ARRA), the Liquid Waste Program at Savannah River site successfully executed forty-one design, procurement, construction, and operating activities in the period from September 2009 through December 2011. Project Management of the program included noteworthy practices involving safety, integrated project teams, communication, and cost, schedule and risk management. Significant upgrades to plant capacity, progress toward waste tank closure and procurement of needed infrastructure were accomplished. Over 1.5 million hours were worked without a single lost work day case. Lessons Learned were continually identified and applied to enhance the program. Investment of Recovery Act monies into the Liquid Waste Program has ensured continued success in the disposition of radioactive wastes and the closure of high level waste tanks at SRS. The funding of a portion of the Liquid Waste Program at SRS by ARRA was a major success. Significant upgrades to plant capacity, progress toward waste tank closure and procurement of needed infrastructure was accomplished. Integrated Project Teams ensured quality products and services were provided to the Operations customers. Over 1.5 million hours were worked without a single lost work day case. Lessons Learned were continually reviewed and reapplied to enhance the program. Investment of Recovery Act monies into the Liquid Waste Program has ensured continued success in the disposition of radioactive wastes and the closure of high level waste tanks at SRS. (authors)

Schmitz, Mark A.; Crouse, Thomas N. [Savannah River Remediation, Aiken, South Carolina 29808 (United States)

2012-07-01T23:59:59.000Z

49

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

SciTech Connect (OSTI)

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

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

1997-12-31T23:59:59.000Z

50

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

51

Microsoft PowerPoint - S05-07_Varona_Solid-Liquid Waste Interface.pptx  

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

Liquid Interface Monitor Liquid Interface Monitor (SLIM) Jose Varona D. Roelant, A. Awwad, D. McDaniel Florida International University's Applied Research Center EM Waste Processing Technical Exchange November 17, 2010 Print Close Disclaimer This presentation was prepared as an account of work sponsored by an agency of the United States government (Department of Energy, Office of Environmental Management, under Grant No. DE-FG01-05EW07033). Neither the United States government nor any agency thereof, nor any of their employees, nor any of its contractors, subcontractors, nor their employees makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness,

52

SOLIEX: A Novel Solid-Liquid Method of Radionuclides Extraction from Radioactive Waste Solutions - 13486  

SciTech Connect (OSTI)

This paper describes recent developments in new solid-liquid extraction method, called SOLIEX, to remove cesium from alkaline solutions. SOLIEX relies on the use of a reversible complexing system comprising a carbon felt bearing molecular traps (calixarenes). This complexing system exhibits a high selectivity for Cs, and is thus expected to be helpful for the treatment of highly diluted cesium wastes even with a high concentration of competing alkali metal cations. As additional advantage, this complexing system can be adapted by molecular engineering to capture other radionuclides, such as Sr, Eu, Am. Finally, this complexing system can be easily and efficiently regenerated by using a cost effective stripping procedure, which limits further generation of waste to meet 'zero liquid' discharge requirements for nuclear facilities. (authors)

Shilova, E.; Viel, P. [CEA Saclay, DSM/IRAMIS/SPCSI, 91191Gif sur Yvette (France)] [CEA Saclay, DSM/IRAMIS/SPCSI, 91191Gif sur Yvette (France); Fournel, B.; Barre, Y. [CEA Marcoule, DTCD, BP17171, 30207 Bagnols sur Ceze (France)] [CEA Marcoule, DTCD, BP17171, 30207 Bagnols sur Ceze (France); Huc, V. [ICMMO - UMR CNRS 8182 - Bat. 420 Universite Paris-Sud (France)] [ICMMO - UMR CNRS 8182 - Bat. 420 Universite Paris-Sud (France)

2013-07-01T23:59:59.000Z

53

Physicochemical Processes Occurring in Long-Term Storage of Liquid Radioactive Waste in Deep Underground Collector Beds  

Science Journals Connector (OSTI)

Interaction under hydrothermal conditions (pressure 3 MPa; temperature 80-170C; contact time up to 2500 h) of intermediate-level acidic waste with bed rock of the underground repository for liquid radioactive...

E. V. Zakharova; E. P. Kaimin; E. N. Darskaya; K. A. Menyailo

2001-07-01T23:59:59.000Z

54

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

E-Print Network [OSTI]

carbon-14, tritium, and iodine-125 liquid scintillation wastes, provided that the activity and isotopes present can be documented. This legislation has generated a significant interest in developing a quick, cost efficient method of identificatior.... Differentiation of various components within a two isotope mixture, and the detection level of a small activity of one nuclide in a large activity of a second radioisotope was examined. A catalogue of spectra, including the isotopic ratio of each component...

Siskel, Robin Lynn

1988-01-01T23:59:59.000Z

55

EA-437; Environmental Assessment Process Equipment Waste and Process Waste Liquid Collection Systems Idaho Chemical Processing Plant Idaho National Engineering Laboratory  

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

437; Environmental Assessment Process Equipment Waste and 437; Environmental Assessment Process Equipment Waste and Process Waste Liquid Collection Systems Idaho Chemical Processing Plant Idaho National Engineering Laboratory TABLE OF CONTENTS Environmental Assessment Process Equipment Waste and Process Waste Liquid Collection Systems Idaho Chemical Processing Plant Idaho National Engineering Laboratory 1. INTRODUCTION 2. DESCRIPTION OF THE PROPOSED ACTION AND ALTERNATIVES 2.1 Purpose and Need of the Proposed Action 2.2 Description of the Affected Facilities 2.3 Description of Proposed Action 2.4 Alternatives to the Proposed Action 2.5 Separate But Related Actions 3. AFFECTED ENVIRONMENT 3.1 Introduction 3.2 Physical Environment 3.3 Biological Resources 3.4 Cultural Resources 3.5 Environmental Quality and Monitoring Programs

56

) L'w LLOAJO>' , Ris-R-516 One-Electron Theory of Metals  

E-Print Network [OSTI]

state of metals as obtained from self- consistent electronic-structure calculations performed by means of Dr. of Science. It is closely related to the review of one-electron calculations of the crystalmmMi--* ? ) L'w LLOAJO>' , Risø-R-516 · $ s x V One-Electron Theory of Metals Cohesive

57

Performance Assessment Program for the Savannah River Site Liquid Waste Facilities - 13610  

SciTech Connect (OSTI)

The Liquid Waste facilities at the U.S. Department of Energy's (DOE) Savannah River Site (SRS) are operated by Liquid Waste Operations contractor Savannah River Remediation LLC (SRR). A separate Performance Assessment (PA) is prepared to support disposal operations at the Saltstone Disposal Facility and closure evaluations for the two liquid waste tank farm facilities at SRS, F-Tank Farm and H-Tank Farm. A PA provides the technical basis and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements identified in operations and closure regulatory guidance. The Saltstone Disposal Facility is subject to a State of South Carolina industrial solid waste landfill permit and the tank farms are subject to a state industrial waste water permit. The three Liquid Waste facilities are also subject to a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Due to the regulatory structure, a PA is a key technical document reviewed by the DOE, the State of South Carolina and the EPA. As the waste material disposed of in the Saltstone Disposal Facility and the residual material in the closed tank farms is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005, the U.S. Nuclear Regulatory Commission (NRC) is also a reviewing agency for the PAs. Pursuant to the Act, the NRC also has a continuing role to monitor disposal actions to assess compliance with stated performance objectives. The Liquid Waste PA program at SRS represents a continual process over the life of the disposal and closure operations. When the need for a PA or PA revision is identified, the first step is to develop a conceptual model to best represent the facility conditions. The conceptual model will include physical dimensions of the closed system, both the engineered and natural system, and modeling input parameters associated with the modeled features, both initial values (at the time of facility closure) and degradation rates/values. During the development of the PA, evaluations are conducted to reflect not only the results associated with the best available information at the time but also to evaluate potential uncertainties and sensitivities associated with the modeled system. While the PA will reflect the modeled system results from the best available information, it will also identify areas for future work to reduce overall PA uncertainties moving forward. DOE requires a PA Maintenance Program such that work continues to reduce model uncertainties, thus bolstering confidence in PA results that support regulatory decisions. This maintenance work may include new Research and Development activities or modeling as informed by previous PA results and other new information that becomes available. As new information becomes available, it is evaluated against previous PAs and appropriate actions are taken to ensure continued confidence in the regulatory decisions. Therefore, the PA program is a continual process that is not just the development of a PA but seeks to incorporate new information to reduce overall model uncertainty and provide continuing confidence in regulatory decisions. (author)

Rosenberger, Kent H. [Savannah River Remediation LLC, Building 705-1C, Aiken, SC 29808 (United States)] [Savannah River Remediation LLC, Building 705-1C, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

58

LOW LEVEL LIQUID RADIOACTIVE WASTE TREATMENT AT MURMANSK, RUSSIA: FACILITY UPGRADE AND EXPANSION  

SciTech Connect (OSTI)

Today there exist many almost overfilled storage tanks with liquid radioactive waste in the Russian Federation. This waste was generated over several years by the civil and military utilization of nuclear power. The current waste treatment capacity is either not available or inadequate. Following the London Convention, dumping of the waste in the Arctic seas is no longer an alternative. Waste is being generated from today's operations, and large volumes are expected to be generated from the dismantling of decommissioned nuclear submarines. The US and Norway have an ongoing co-operation project with the Russian Federation to upgrade and expand the capacity of a treatment facility for low level liquid waste at the RTP Atomflot site in Murmansk. The capacity will be increased from 1,200 m{sup 3}/year to 5,000 m{sup 3} /year. The facility will also be able to treat high saline waste. The construction phase will be completed the first half of 1998. This will be followed by a start-up and a one year post-construction phase, with US and Norwegian involvement for the entire project. The new facility will consist of 9 units containing various electrochemical, filtration, and sorbent-based treatment systems. The units will be housed in two existing buildings, and must meet more stringent radiation protection requirements that were not enacted when the facility was originally designed. The US and Norwegian technical teams have evaluated the Russian design and associated documentation. The Russian partners send monthly progress reports to US and Norway. Not only technical issues must be overcome but also cultural differences resulting from different methods of management techniques. Six to eight hour time differentials between the partners make real time decisions difficult and relying on electronic age tools becomes extremely important. Language difficulties is another challenge that must be solved. Finding a common vocabulary, and working through interpreters make the process very vulnerable. Each of these obstacles can be overcome when there is a common goal and vision shared by all parties and adequate funds are provided to accomplish the task. The upgrading and expansion of this facility and the construction of a similar facility on the Far East coast of Russia will enable the Russians to sign the London Convention dumping prohibition. This project is one of the first waste management construction projects in the north-west of Russia with foreign contribution. Its success may open for additional co-operative projects with Russia in the future.

BOWERMAN,B.; CZAJKOWSKI,C.; DYER,R.S.; SORLIE,A.

2000-03-01T23:59:59.000Z

59

Treatment requirements for decontamination of ORNL low-level liquid waste  

SciTech Connect (OSTI)

Experimental studies have been made to provide data for the development of improved processes for decontaminating low-level liquid wastes (LLLWs) that exist and continue to be generated at Oak Ridge National Laboratory. The concept underlying this work is that there is a net benefit if the major radionuclides ({sup 137}Cs, {sup 134}Cs, {sup 90}Sr, and actinides) can be separated into small volumes, thereby reducing the activity of the bulk of the waste so that it can be disposed of or managed at a lower total cost. Data-base calculations on the LLLW supernate and sludges contained in the active Melton Valley Storage Tanks and evaporator storage and service tanks are essential in order to define and determine the extent of the problem. These calculations indicate to what extent alpha- and beta-gamma-emitting radionuclides must be removed and/or treated before final disposition of the waste can be made. They also show that many of the inorganic constitutents (e.g., regulated metals and nitrate) and minor radionuclides such as {sup 14}C and actinides (in terms of quantity present) must be removed before the LLLW can be disposed of as either liquid to the environment or solidified and disposed of as solid NUS Class L-1 or L-2 LLW. 25 refs., 31 tabs.

Lee, D.D.; Campbell, D.O.

1991-10-01T23:59:59.000Z

60

Treatment of low-level radioactive waste liquid by reverse osmosis  

SciTech Connect (OSTI)

The processing of low-level radioactive waste (LLRW) liquids that result from operation of nuclear power plants with reverse osmosis systems is not common practice. A demonstration facility is operating at Chalk River Laboratories (of Atomic Energy of Canada Limited), processing much of the LLRW liquids generated at the site from a multitude of radioactive facilities, ranging from isotope production through decontamination operations and including chemical laboratory drains. The reverse osmosis system comprises two treatment steps--spiral wound reverse osmosis followed by tubular reverse osmosis--to achieve an average volume reduction factor of 30:1 and a removal efficiency in excess of 99% for most radioactive and chemical species. The separation allows the clean effluent to be discharged without further treatment. The concentrated waste stream of 3 wt% total solids is further processed to generate a solid product. The typical lifetimes of the membranes have been nearly 4000 hours, and replacement was required based on increased pressure drops and irreversible loss of permeate flux. Four years of operating experience with the reverse osmosis system, to demonstrate its practicality and to observe and record its efficiency, maintenance requirements and effectiveness, have proven it to be viable for volume reduction and concentration of LLRW liquids generated from nuclear-power-plant operations.

Buckley, L.P.; Sen Gupta, S.K.; Slade, J.A. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada). Chalk River Labs.

1995-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Waste Tank Organic Safety Project: Analysis of liquid samples from Hanford waste tank 241-C-103  

SciTech Connect (OSTI)

A suite of physical and chemical analyses has been performed in support of activities directed toward the resolution of an Unreviewed Safety Question concerning the potential for a floating organic layer in Hanford waste tank 241-C-103 to sustain a pool fire. The analysis program was the result of a Data Quality Objectives exercise conducted jointly with staff from Westinghouse Hanford Company and Pacific Northwest Laboratory (PNL). The organic layer has been analyzed for flash point, organic composition including volatile organics, inorganic anions and cations, radionuclides, and other physical and chemical parameters needed for a safety assessment leading to the resolution of the Unreviewed Safety Question. The aqueous layer underlying the floating organic material was also analyzed for inorganic, organic, and radionuclide composition, as well as other physical and chemical properties. This work was conducted to PNL Quality Assurance impact level III standards (Good Laboratory Practices).

Pool, K.H.; Bean, R.M.

1994-03-01T23:59:59.000Z

62

Waste Characterization Data Manual for the inactive liquid low-level waste tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program  

SciTech Connect (OSTI)

This Waste Characterization Data Manual contains the results of an analysis of the contents of liquid low-level waste (LLLW) tanks that have been removed from service in accordance with the requirements of the Oak Ridge National Laboratory (ORNL) Federal Facility Agreement (FFA), Section IX.G.1. Section IX.G.1 of the FFA requires waste characterizations be conducted and provided to EPA and TDEC for all LLLW tanks that are removed from service. These waste characterizations shall include the results of sampling and analysis of the tank contents, including wastes, liquids, and sludges. This manual was first issued as ORNL/ER-80 in June 1992. The waste characterization data were extracted from ORNL reports that described tank sampling and analysis conducted in 1988 for 32 out-of-service tanks. This revision of the manual contains waste characterization data for 54 tanks, including the 32 tanks from the 1988 sampling campaign (Sects. 2.1 through 2.32) and the 22 additional tanks from a subsequent sampling campaign in 1992 and 1993 (Sects. 2.33 through 2.54). Data are presented from analyses of volatile organic compounds, semivolatile organic compounds, polychlorinated biphenyls (PCBs), pesticides, radiochemical compounds, and inorganic compounds. As additional data resulting from analyses of out-of-service tank samples become available, they will be added to this manual.

Not Available

1993-06-01T23:59:59.000Z

63

File:DIA Kenya 0906 lw (2).pdf | Open Energy Information  

Open Energy Info (EERE)

DIA Kenya 0906 lw (2).pdf DIA Kenya 0906 lw (2).pdf Jump to: navigation, search File File history File usage File:DIA Kenya 0906 lw (2).pdf Size of this preview: 800 × 600 pixels. Go to page 1 2 3 4 5 6 7 8 9 10 Go! next page → next page → Full resolution ‎(1,500 × 1,125 pixels, file size: 896 KB, MIME type: application/pdf, 10 pages) File history Click on a date/time to view the file as it appeared at that time. Date/Time Thumbnail Dimensions User Comment current 10:07, 21 September 2012 Thumbnail for version as of 10:07, 21 September 2012 1,500 × 1,125, 10 pages (896 KB) Gjones (Talk | contribs) You cannot overwrite this file. Edit this file using an external application (See the setup instructions for more information) File usage The following page links to this file: Webinar on Development Impact Assessment for Low Emissions

64

EMSL - liquids  

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

liquids en Iodine Solubility in Low-Activity Waste Borosilicate Glass at 1000 C. http:www.emsl.pnl.govemslwebpublicationsiodine-solubility-low-activity-waste-borosilicate...

65

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

SciTech Connect (OSTI)

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.

Coenenberg, J.G.

1997-08-15T23:59:59.000Z

66

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

SciTech Connect (OSTI)

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

Brown, A.

2014-04-27T23:59:59.000Z

67

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

SciTech Connect (OSTI)

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

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

1990-09-01T23:59:59.000Z

68

Isolation of metals from liquid wastes: Reactive scavenging in turbulent thermal reactors. 1998 annual progress report  

SciTech Connect (OSTI)

'The objective of this project is to develop the fundamental science base necessary to assess the utility of high-temperature processes to volatilize metals in DOE metal-bearing liquid wastes, so that they can be reactively scavenged by sorbents. The problem is addressed through a collaborative research program involving a team of five senior scientists and their respective laboratories, at four institutions. Specific goals are to: (1) Understand high-temperature reaction kinetics between sorbent substrates and certain volatile and semi-volatile metals in the DOE liquid waste inventory (e.g., Cs and Sr), using a laminar-flow reactor for which extraction of kinetic data is not complicated by turbulence; (2) Develop models to predict both trajectories of individual droplets in turbulent high-temperature reactors, and rates of metal evolution from droplets, and compare model predictions with experimental data from a pilot-scale turbulent thermal reactor; (3) Connect the reaction kinetic models with the droplet trajectory/mass evolution models, in order to predict and optimize metal scavenging processes in turbulent-flow reactors, and to test these combined models against data taken from a turbulent high temperature reactor. This report summarizes work at a point midway through the first year of a 3-year project. At the University of Arizona (UA), two tasks are underway. The first task is concerned with attempting to understand high-temperature reaction kinetics between sorbent substrates and certain volatile and semi-volatile metals. The second task is concerned with applying Kerstein''s One Dimensional Turbulence model to prediction of droplet trajectories in turbulent flow.'

Wendt, J.O.L. [Univ. of Arizona, Tucson, AZ (US); Linak, W.P. [Environmental Protection Agency, Research Triangle Park, NC (US); Kerstein, A.R. [Sandia National Labs., Livermore, CA (US); Pearlstein, A.J.; Scheeline, A. [Univ. of Illinois, Urbana, IL (US)

1998-06-01T23:59:59.000Z

69

CERTIFICATION DOCKET FOR THE F0RhqE.R SITE OF THE RADIOACTIVE LIQUID WASTE TREATMENT PLANT (TA-45)  

Office of Legacy Management (LM)

CERTIFICATION DOCKET CERTIFICATION DOCKET FOR THE F0RhqE.R SITE OF THE RADIOACTIVE LIQUID WASTE TREATMENT PLANT (TA-45) AND THE EFFLUENT RECEIVING AREAS OF ACID, PUEBLO, AND LOS ALAMOS CANYOM, LOS ALAMOS, NEW MEXICO DEPARTMENT OF ENERGY Office of Nuclear Energy Office of Terminal Waste Disposal and Remedial Action Division of Remedial Action Projects -. CONTENTS A Page - Introduction to the Certification Docket for the Former Site of the Radioactive Liquid Waste Treatment Plant (TA-45) and the Effluent Receiving Areas of Acid, Pueblo, and Los Alamos Canyons, Los Alamos, New Mexico Description of the Formeriy Utilized Sites Program at the Former Site of the T.4-45 Treatment Plant and Acid, Pueblo, and Los Alamos Canyons Purpose Property Identification Docket Contents

70

222-S radioactive liquid waste line replacement and 219-S secondary containment upgrade, Hanford Site, Richland, Washington  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) is proposing to: (1) replace the 222-S Laboratory (222-S) radioactive liquid waste drain lines to the 219-S Waste Handling Facility (219-S); (2) upgrade 219-S by replacing or upgrading the waste storage tanks and providing secondary containment and seismic restraints to the concrete cells which house the tanks; and (3) replace the transfer lines from 219-S to the 241-SY Tank Farm. This environmental assessment (EA) has been prepared in compliance with the National Environmental Policy Act (NEPA) of 1969, as amended, the Council on Environmental Quality Regulations for Implementing the Procedural Provisions of NEPA (40 Code of Federal Regulations [CFR] 1500-1508), and the DOE Implementing Procedures for NEPA (10 CFR 1021). 222-S is used to perform analytical services on radioactive samples in support of the Tank Waste Remediation System and Hanford Site environmental restoration programs. Activities conducted at 222-S include decontamination of analytical processing and support equipment and disposal of nonarchived radioactive samples. These activities generate low-level liquid mixed waste. The liquid mixed waste is drained through pipelines in the 222-S service tunnels and underground concrete encasements, to two of three tanks in 219-S, where it is accumulated. 219-S is a treatment, storage, and/or disposal (TSD) unit, and is therefore required to meet Washington Administrative Code (WAC) 173-303, Dangerous Waste Regulations, and the associated requirements for secondary containment and leak detection. The service tunnels are periodically inspected by workers and decontaminated as necessary to maintain as low as reasonably achievable (ALARA) radiation levels. Although no contamination is reaching the environment from the service tunnels, the risk of worker exposure is present and could increase. 222-S is expected to remain in use for at least the next 30 years to serve the Hanford Site environmental cleanup mission.

NONE

1995-01-01T23:59:59.000Z

71

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

SciTech Connect (OSTI)

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

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

2011-01-12T23:59:59.000Z

72

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

SciTech Connect (OSTI)

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)

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

2013-07-01T23:59:59.000Z

73

Microsoft Word - FINAL 7-12-10 Site Visit Report - LANL Radioactive Liquid Waste Facility FCA.docx  

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

Site Visit Report Facility Centered Assessment of the Los Alamos National Laboratory Radioactive Liquid Waste Treatment Facility - June 2010 This site visit report documents the results of the Office of Health, Safety and Security's (HSS) review of the Facility Centered Assessment (FCA) of the Los Alamos National Laboratory (LANL) Radioactive Liquid Waste Treatment Facility (RLW). This review, conducted June 9-25, 2010, was sponsored by the U.S. Department of Energy (DOE) Los Alamos Site Office (LASO) and LANL, and conducted jointly by HSS, LASO, and LANL staff. The Office of Environment, Safety and Health Evaluations was the overall lead organization for evaluation of the FCA process with the participation of the LASO Facility Representative assigned to RLW.

74

Precipitation of cesium jointly with uranium from nitric acid liquid radioactive wastes to obtain solid matrices for long-term storage  

Science Journals Connector (OSTI)

The possibility of converting liquid radioactive wastes containing Cs into chemically and thermodynamically stable...4U5O17...can be prepared by different procedures. The resulting compounds are characterized by ...

Yu. I. Korneiko; A. A. Murzin; O. V. Shmidt

2009-08-01T23:59:59.000Z

75

Evaluation of DMDOHEMA based supported liquid membrane system for high level waste remediation under simulated conditions  

Science Journals Connector (OSTI)

Abstract N,N?-dimethyl-N,N?-dioctyl-2,(2?-hexyloxyethyl) malonamide (DMDOHEMA) has been proposed as solvent for the partitioning of radiotoxic minor actinides from high-level waste (HLW) solutions. The facilitated transport of 241Am(III), 239Pu(IV), 233U(VI), 237Np(V) across supported liquid membrane (SLM) impregnated with DMDOHEMA solution in n-dodecane was investigated under varying conditions of feed acidity, receiver phase composition, carrier concentration, and membrane thickness. Micro porous PTFE membrane was used as the polymeric support. There was a decrease in the transport of metal ions under the pressurized heavy water reactor simulated HLW (PHWR-SHLW) conditions. The physical stability of the SLM impregnated with the carrier was investigated for ~60 days by performing Am(III) permeation studies. Marginal variation in the transport behavior suggested reasonably good stability of the impregnated carrier in the membrane pores. A simple mathematical model has been developed to simulate experimental data and to explain quantitatively the role of different parameters.

Ajay B. Patil; Pankaj Kandwal; V.S. Shinde; P.N. Pathak; P.K. Mohapatra

2013-01-01T23:59:59.000Z

76

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

Broader source: Energy.gov [DOE]

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

77

Summary - WTP HLW Waste Vitrification Facility  

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

W W HLW W DOE is Immob site's t facilitie Facility to iden the HL to be i norma The as along w Level ( * H * H * H Sy * Pu D The Ele Site: H roject: W Report Date: M ited States Waste T Why DOE Waste Vitrificatio s constructing bilization Plant tank wastes. T es including a H y (HLW). The ntify the critical LW and determ ncorporated in ally requires a T What th ssessment team with each elem (TRL) for the H LW Melter Fee LW Melter Pro LW Melter Offg ystem/Process ulse Jet Mixer isposal System To view the full T http://www.em.doe. objective of a Tech ements (CTEs), usin Hanford/ORP Waste Treatme March 2007 Departmen Treatmen W E-EM Did This n Facility a Waste Treat (WTP) at Hanf The WTP is com High-Level Wa purpose of this technology ele mine if these are to the final WT Technology Re he TRA Team m identified the

78

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

SciTech Connect (OSTI)

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

Wilmarth, B; Sheryl Bush, S

2008-10-31T23:59:59.000Z

79

Cylinder wall waste heat recovery from liquid-cooled internal combustion engines utilizing thermoelectric generators.  

E-Print Network [OSTI]

?? This report is a dissertation proposal that focuses on the energy balance within an internal combustion engine with a unique coolant-based waste heat recovery (more)

Armstead, John Randall

2012-01-01T23:59:59.000Z

80

Feasibility study on the solidification of liquid low-level radioactive mixed waste in the inactive tank system at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

A literature survey was conducted to help determine the feasibility of solidifying a liquid low-level radioactive mixed waste in the inactive tank system at Oak Ridge National Laboratory (ORNL). The goal of this report is to facilitate a decision on the disposition of these wastes by identifying any waste constituents that might (1) compromise the strength or stability of the waste form or (2) be highly leachable. Furthermore, its goal is to identify ways to circumvent interferences and to decrease the leachability of the waste constituents. This study has sought to provide an understanding of inhibition of cement set by identifying the fundamental chemical mechanisms by which this inhibition takes place. From this fundamental information, it is possible to draw some conclusions about the potential effects of waste constituents, even in the absence of particular studies on specific compounds.

Trussell, S. (Texas A and M Univ., College Station, TX (United States). Dept. of Civil Engineering); Spence, R.D. (Oak Ridge National Lab., TN (United States))

1993-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Engineering assessment of low-level liquid waste disposal caisson locations at the 618-11 Burial Grounds  

SciTech Connect (OSTI)

Rockwell Hanford Operations is currently involved in an extensive effort to perform interim ground surface stabilization activities at retired low-level waste burial grounds located at the Hanford Site, Richland, Washington. The principal objective of these activities is to promote increased occupational and radiological safety at burial grounds. Interim stabilization activities include: (1) load testing (traversing burial ground surfaces with heavy equipment to promote incipient collapse of void spaces within the disposal structure and overburden), (2) barrier placement (placement of a {ge} 0.6 m soil barrier over existing overburden), and (3) revegetation (establishment of shallow rooted vegetation on the barrier to mitigate deep rooted plant growth and to reduce erosion). Low-level waste disposal caissons were used in 300 Area Burial Grounds as internment structures for containerized liquid wastes. These caissons, by virtue of their contents, design and methods of closure, require long-term performance evaluation. As an initial activity to evaluate long-term performance, the accurate location of these structures is required. This topical report summarizes engineering activities used to locate caissons in the subsurface environment at the Burial Ground. Activities were conducted to locate caissons during surface stabilization activities. The surface locations were marked, photographed, and recorded on an as built engineering drawing. The recorded location of these caissons will augment long-term observations of confinement structure and engineered surface barrier performance. In addition, accurate caisson location will minimize occupational risk during monitoring and observation activities periodically conducted at the burial ground.

Phillips, S.J.; Fischer, D.D.; Crawford, R.C. [Westinghouse Hanford Co., Richland, WA (United States); Rising, J.L. [Pacific Northwest Lab., Richland, WA (United States)

1982-06-01T23:59:59.000Z

82

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)

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.

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.

1994-12-01T23:59:59.000Z

83

State-of-the-art of liquid waste disposal for geothermal energy systems: 1979. Report PNL-2404  

SciTech Connect (OSTI)

The state-of-the-art of geothermal liquid waste disposal is reviewed and surface and subsurface disposal methods are evaluated with respect to technical, economic, legal, and environmental factors. Three disposal techniques are currently in use at numerous geothermal sites around the world: direct discharge into surface waters; deep-well injection; and ponding for evaporation. The review shows that effluents are directly discharged into surface waters at Wairakei, New Zealand; Larderello, Italy; and Ahuachapan, El Salvador. Ponding for evaporation is employed at Cerro Prieto, Mexico. Deep-well injection is being practiced at Larderello; Ahuachapan; Otake and Hatchobaru, Japan; and at The Geysers in California. All sites except Ahuachapan (which is injecting only 30% of total plant flow) have reported difficulties with their systems. Disposal techniques used in related industries are also reviewed. The oil industry's efforts at disposal of large quantities of liquid effluents have been quite successful as long as the effluents have been treated prior to injection. This study has determined that seven liquid disposal methods - four surface and three subsurface - are viable options for use in the geothermal energy industry. However, additional research and development is needed to reduce the uncertainties and to minimize the adverse environmental impacts of disposal. (MHR)

Defferding, L.J.

1980-06-01T23:59:59.000Z

84

Radioactive Waste: 1. Radioactive waste from your lab is  

E-Print Network [OSTI]

Radioactive Waste: 1. Radioactive waste from your lab is collected by the RSO. 2. Dry radioactive waste must be segregated by isotope. 3. Liquid radioactive waste must be separated by isotope. 4. Liquid frequently and change them if contaminated. 5. Use radioactive waste container to collect the waste. 6. Check

Jia, Songtao

85

Low-level liquid radioactive waste treatment at Murmansk, Russia: Technical design and review of facility upgrade and expansion  

SciTech Connect (OSTI)

The governments of Norway and the US have committed their mutual cooperation and support the Murmansk Shipping Company (MSCo) to expand and upgrade the Low-Level Liquid Radioactive Waste (LLRW) treatment system located at the facilities of the Russian company RTP Atomflot, in Murmansk, Russia. RTP Atomflot provides support services to the Russian icebreaker fleet operated by the MSCo. The objective is to enable Russia to permanently cease disposing of this waste in Arctic waters. The proposed modifications will increase the facility`s capacity from 1,200 m{sup 3} per year to 5,000 m{sup 3} per year, will permit the facility to process high-salt wastes from the Russian Navy`s Northern fleet, and will improve the stabilization and interim storage of the processed wastes. The three countries set up a cooperative review of the evolving design information, conducted by a joint US and Norwegian technical team from April through December, 1995. To ensure that US and Norwegian funds produce a final facility which will meet the objectives, this report documents the design as described by Atomflot and the Russian business organization, ASPECT, both in design documents and orally. During the detailed review process, many questions were generated, and many design details developed which are outlined here. The design is based on the adsorption of radionuclides on selected inorganic resins, and desalination and concentration using electromembranes. The US/Norwegian technical team reviewed the available information and recommended that the construction commence; they also recommended that a monitoring program for facility performance be instituted.

Dyer, R.S.; Diamante, J.M. [Environmental Protection Agency, Washington, DC (United States). Office of International Activities; Duffey, R.B. [Brookhaven National Lab., Upton, NY (United States)] [and others

1996-07-01T23:59:59.000Z

86

Savannah River Sites Liquid Waste Operations Adds Multi-Functional Laboratory  

Broader source: Energy.gov [DOE]

AIKEN, S.C. A new multi-functional laboratory supporting high-level waste processing at the Savannah River Site (SRS) gives workers a new and improved place to provide back-up laboratory support and more space for chemical storage.

87

A Comparative Review of Hydrologic Issues Involved in Geologic Storage of CO2 and Injection Disposal of Liquid Waste  

SciTech Connect (OSTI)

The paper presents a comparison of hydrologic issues and technical approaches used in deep-well injection and disposal of liquid wastes, and those issues and approaches associated with injection and storage of CO{sub 2} in deep brine formations. These comparisons have been discussed in nine areas: (1) Injection well integrity; (2) Abandoned well problems; (3) Buoyancy effects; (4) Multiphase flow effects; (5) Heterogeneity and flow channeling; (6) Multilayer isolation effects; (7) Caprock effectiveness and hydrogeomechanics; (8) Site characterization and monitoring; and (9) Effects of CO{sub 2} storage on groundwater resources There are considerable similarities, as well as significant differences. Scientifically and technically, these two fields can learn much from each other. The discussions presented in this paper should help to focus on the key scientific issues facing deep injection of fluids. A substantial but by no means exhaustive reference list has been provided for further studies into the subject.

Tsang, C.-F.; Birkholzer, J.; Rutqvist, J.

2008-04-15T23:59:59.000Z

88

Application of curium measurements for safeguarding at reprocessing plants. Study 1: High-level liquid waste and Study 2: Spent fuel assemblies and leached hulls  

SciTech Connect (OSTI)

In large-scale reprocessing plants for spent fuel assemblies, the quantity of plutonium in the waste streams each year is large enough to be important for nuclear safeguards. The wastes are drums of leached hulls and cylinders of vitrified high-level liquid waste. The plutonium amounts in these wastes cannot be measured directly by a nondestructive assay (NDA) technique because the gamma rays emitted by plutonium are obscured by gamma rays from fission products, and the neutrons from spontaneous fissions are obscured by those from curium. The most practical NDA signal from the waste is the neutron emission from curium. A diversion of waste for its plutonium would also take a detectable amount of curium, so if the amount of curium in a waste stream is reduced, it can be inferred that there is also a reduced amount of plutonium. This report studies the feasibility of tracking the curium through a reprocessing plant with neutron measurements at key locations: spent fuel assemblies prior to shearing, the accountability tank after dissolution, drums of leached hulls after dissolution, and canisters of vitrified high-level waste after separation. Existing pertinent measurement techniques are reviewed, improvements are suggested, and new measurements are proposed. The authors integrate these curium measurements into a safeguards system.

Rinard, P.M.; Menlove, H.O.

1996-03-01T23:59:59.000Z

89

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

SciTech Connect (OSTI)

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

Dziewinski, J.J.

1998-09-28T23:59:59.000Z

90

Enterprise Assessments Operational Awareness Record, Waste Treatment...  

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

Observation of Waste Treatment and Immobilization Plant High Level Waste Facility Radioactive Liquid Waste Disposal System Hazards Analysis Activities (EA-WTP-HLW-2014-08-18(a))...

91

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

SciTech Connect (OSTI)

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

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

2014-01-07T23:59:59.000Z

92

Flowsheet model for the electrochemical treatment of liquid radioactive wastes. Final report  

SciTech Connect (OSTI)

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

Hobbs, D.T. [Westinghouse Savannah River Co., Aiken, SC (United States); Prasad, S.; Farell, A.E.; Weidner, J.W.; White, R.E. [South Carolina Univ., Columbia, SC (United States). Dept. of Chemical Engineering

1995-12-31T23:59:59.000Z

93

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

SciTech Connect (OSTI)

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

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

1982-03-05T23:59:59.000Z

94

Studies on fish waste management practices in Aroor Seafood Industrial Belt, Kerala and conversion of seafood waste into a liquid plant growth supplement.  

E-Print Network [OSTI]

??This study was materialized to analyze the management issues regarding the seafood processing waste generated including its impact on the coastal community in one of (more)

Abhilash, S

2013-01-01T23:59:59.000Z

95

WASTE DESCRIPTION TYPE OF PROJECT POUNDS REDUCED,  

E-Print Network [OSTI]

DESCRIPTION DETAILS * Radioactive Waste Source Reduction 1,500 Radioactive Waste $6,000 $2,500 $6,000 Waste Yard Sorting Table surveying to sort clean waste from radioactive waste Radioactive Emissions Emission lives. Radioactive Waste generated through wet chemistry Waste Minimization 30 Mixed waste / Liquid

96

Ceramicrete stabilization of radioactive-salt-containing liquid waste and sludge water. Final CRADA report.  

SciTech Connect (OSTI)

It was found that the Ceramicrete Specimens incorporated the Streams 1 and 2 sludges with the adjusted loading about 41.6 and 31.6%, respectively, have a high solidity. The visible cracks in the matrix materials and around the anionite AV-17 granules included could not obtain. The granules mentioned above fixed by Ceramicrete matrix very strongly. Consequently, we can conclude that irradiation of Ceramecrete matrix, goes from the high radioactive elements, not result the structural degradation. Based on the chemical analysis of specimens No.462 and No.461 used it was shown that these matrix included the formation elements (P, K, Mg, O), but in the different samples their correlations are different. These ratios of the content of elements included are about {+-} 10%. This information shows a great homogeneity of matrix prepared. In the list of the elements founded, expect the matrix formation elements, we detected also Ca and Si (from the wollastonite - the necessary for Ceramicrete compound); Na, Al, S, O, Cl, Fe, Ni also have been detected in the Specimen No.642 from the waste forms: NaCl, Al(OH){sub 3}, Na{sub 2}SO{sub 4}. Fe(OH){sub 3}, nickel ferrocyanide and Ni(NO{sub 3})2. The unintelligible results also were found from analysis of an AV-17 granules, in which we obtain the great amount of K. The X-ray radiographs of the Ceramicrete specimens with loading 41.4 % of Stream 1 and 31.6% of Stream 2, respectively showed that the realization of the advance technology, created at GEOHKI, leads to formation of excellent ceramic matrix with high amount of radioactive streams up to 40% and more. Really, during the interaction with start compounds MgO and KH{sub 2}PO{sub 4} with the present of H{sub 3}BO{sub 3} and Wollastonite this process run with high speed under the controlled regimes. That fact that the Ceramicrete matrix with 30-40% of Streams 1 and 2 have a crystalline form, not amorphous matter, allows to permit that these matrix should be very stable, reliable for incorporation of a radionuclides.

Ehst, D.; Nuclear Engineering Division

2010-08-04T23:59:59.000Z

97

Numerical simulation of hydrothermal salt separation process and analysis and cost estimating of shipboard liquid waste disposal  

E-Print Network [OSTI]

Due to environmental regulations, waste water disposal for US Navy ships has become a requirement which impacts both operations and the US Navy's budget. In 2006, the cost for waste water disposal Navy-wide was 54 million ...

Hunt, Andrew Robert

2007-01-01T23:59:59.000Z

98

Department of Energy Issues Final Request for Proposals for Savannah...  

Energy Savers [EERE]

and disposition of liquid wastes, and the operational closure of the LW storage tanks. The RFP describes the criteria DOE will use in evaluating the proposals received. The...

99

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

SciTech Connect (OSTI)

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)

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

2013-07-01T23:59:59.000Z

100

Structural Integrity Program for the 300,000-Gallon Radioactive Liquid Waste Storage Tanks at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect (OSTI)

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.

Bryant, Jeffrey W.

2010-08-12T23:59:59.000Z

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

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

Broader source: Energy.gov [DOE]

Biomass is a renewable energy resource that can be converted into liquid fuel suitable for transportation applications and thus help meet the Energy Independence and Security Act renewable energy goals (U.S. Congress 2007). However, biomass is not always available in sufficient quantity at a price compatible with fuels production. Municipal solid waste (MSW) on the other hand is readily available in large quantities in some communities and is considered a partially renewable feedstock. Furthermore, MSW may be available for little or no cost.

102

Resource-Limited Multiattribute Value Analysis of Alternatives for Immobilizing Radioactive Liquid Process Waste Stored in Saluggia, Italy  

Science Journals Connector (OSTI)

This large Italian public works project started with the development of engineering data to support the evaluation of three alternatives for processing nuclear waste. After an analysis of the alternatives' performance from an engineering perspective ... Keywords: EUREX, Sogin, alternatives, applications, decision analysis, decision making, decision theory, energy, environment, multiattribute value analysis, nuclear waste

Alan J. Brothers; Shas V. Mattigod; Denis M. Strachan; Gordon H. Beeman; Paul K. Kearns; Angelo Papa; Carlo Monti

2009-06-01T23:59:59.000Z

103

Feasibility study on the solidification of liquid low-level radioactive mixed waste in the inactive tank system at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program  

SciTech Connect (OSTI)

A literature survey was conducted to help determine the feasibility of solidifying a liquid low-level radioactive mixed waste in the inactive tank system at Oak Ridge National Laboratory (ORNL). The goal of this report is to facilitate a decision on the disposition of these wastes by identifying any waste constituents that might (1) compromise the strength or stability of the waste form or (2) be highly leachable. Furthermore, its goal is to identify ways to circumvent interferences and to decrease the leachability of the waste constituents. This study has sought to provide an understanding of inhibition of cement set by identifying the fundamental chemical mechanisms by which this inhibition takes place. From this fundamental information, it is possible to draw some conclusions about the potential effects of waste constituents, even in the absence of particular studies on specific compounds.

Trussell, S. [Texas A and M Univ., College Station, TX (United States). Dept. of Civil Engineering; Spence, R.D. [Oak Ridge National Lab., TN (United States)

1993-01-01T23:59:59.000Z

104

Low-Level Liquid Waste Processing Pilot Studies Using a Vibratory Shear Enhancing Process (VSEP) for Filtration  

SciTech Connect (OSTI)

A previous EPRI study evaluated potential treatment methods for the removal of iron from BWR waste streams. Of the methods investigated, high shear filtration using the vibratory shear-enhanced process (VSEP) showed the most promise to effectively and economically remove high iron concentrations from backwash receiving tank waste. A VSEP filter uses oscillatory vibration to create high shear at the surface of the filter membrane. This high shear force significantly improves the filter's resistance to fouling thereby enabling high throughputs with very little secondary waste generation. With a VSEP filter, the waste feed stream is split into two effluents- a permeate stream with little or no suspended solids and a concentrate stream with a suspended solids concentration much higher than that of the feed stream. To evaluate the feasibility of using a VSEP concept for processing typical high iron containing BWR radwaste, a surrogate feedstream containing up to 1,700 ppm iron oxide (as Fe2O3) was used. This surrogate waste simulates radioactive waste found at Exelon's Limerick and Peach Bottom (powdered resin condensate) plants, and in Hope Creek's (deep bed condensate) radwaste systems. Testing was done using a series L (laboratory scale) VSEP unit at the manufacturer's and contractor's laboratories. These tests successfully demonstrated the VSEP capability for producing highly concentrated waste streams with totally ''recyclable'' permeate (e.g., greater than 95% recovery).

Bushart, S.; Tran, P.; Asay, R.

2002-02-25T23:59:59.000Z

105

Enterprise Assessments Operational Awareness Record, Waste Treatment...  

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

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

106

Assessment of fission product content of high-level liquid waste supernate on E-Area vault package criteria  

SciTech Connect (OSTI)

This report assesses the tank farm`s high level waste supernate to determine any potential impacts on waste certification for the E-Area vaults (EAV). The Waste Acceptance Criteria procedure (i.e., WAC 3.10 of the 1S manual) imposes administrative controls on radioactive material in waste packages sent to the EAV, specifically on six fission products. Waste tank supernates contain various fission products, so any waste package containing material contaminated with supernate will contain these radioactive isotopes. This report develops the process knowledge basis for characterizing the supernate composition for these isotopes, so that appropriate controls can be implemented to ensure that the EAV WAC is met. Six fission products are listed in the SRS 1S Manual WAC 3.10: Se-79, which decays to bromine; Sr-90, which decays to niobium; Tc-99, which decays to ruthenium; Sn-126, which decays to tellurium; I-129, which decays to xenon; and Cs-137, which decays to barium.

Brown, D.F.

1994-06-30T23:59:59.000Z

107

Evaluation of plasma melter technology for verification of high-sodium content low-level radioactive liquid wastes: Demonstration test No. 4 preliminary test report  

SciTech Connect (OSTI)

This document provides a preliminary report of plasma arc vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System Low-Level Waste (LLW) Vitrification Program. Phase I test conduct included 26 hours (24 hours steady state) of melting of simulated high-sodium low-level radioactive liquid waste. Average processing rate was 4.9 kg/min (peak rate 6.2 kg/min), producing 7330 kg glass product. Free-flowing glass pour point was 1250 C, and power input averaged 1530 kW(e), for a total energy consumption of 19,800 kJ/kg glass. Restart capability was demonstrated following a 40-min outage involving the scrubber liquor heat exchanger, and glass production was continued for another 2 hours. Some volatility losses were apparent, probably in the form of sodium borates. Roughly 275 samples were collected and forwarded for analysis. Sufficient process data were collected for heat/material balances. Recommendations for future work include lower boron contents and improved tuyere design/operation.

McLaughlin, D.F.; Gass, W.R.; Dighe, S.V.; D`Amico, N.; Swensrud, R.L.; Darr, M.F.

1995-01-10T23:59:59.000Z

108

Cesium removal from liquid acidic wastes with the primary focus on ammonium molybdophosphate as an ion exchanger: A literature review  

SciTech Connect (OSTI)

Many articles have been written concerning the selective removal of cesium from both acidic and alkaline defense wastes. The majority of the work performed for cesium removal from defense wastes involves alkaline feed solutions. Several different techniques for cesium removal from acidic solutions have been evaluated such as precipitation, solvent extraction, and ion exchange. The purpose of this paper is to briefly review various techniques for cesium removal from acidic solutions. The main focus of the review will be on ion exchange techniques, particularly those involving ammonium molybdophosphate as the exchanger. The pertinent literature sources are condensed into a single document for quick reference. The information contained in this document was used as an aid in determining techniques to evaluate cesium removal from the acidic Idaho Chemical Processing Plant waste matrices. 47 refs., 2 tabs.

Miller, C.J.

1995-03-01T23:59:59.000Z

109

Savannah River Site Achieves Waste Transfer First  

Broader source: Energy.gov [DOE]

AIKEN, S.C. The EM program and its liquid waste contractor at the Savannah River Site (SRS) made history recently by safely transferring radioactive liquid waste from F Tank Farm to H Tank Farm using a central control room.

110

The largest radioactive waste glassification  

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

largest radioactive waste glassification largest radioactive waste glassification plant in the nation, the Defense Waste Processing Facility (DWPF) converts the liquid nuclear waste currently stored at the Savannah River Site (SRS) into a solid glass form suitable for long-term storage and disposal. Scientists have long considered this glassification process, called "vitrification," as the preferred option for treating liquid nuclear waste. By immobilizing the radioactivity in glass, the DWPF reduces the risks associated with the continued storage of liquid nuclear waste at SRS and prepares the waste for final disposal in a federal repository. About 38 million gallons of liquid nuclear wastes are now stored in 49 underground carbon-steel tanks at SRS. This waste has about 300 million curies of radioactivity, of which the vast majority

111

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

SciTech Connect (OSTI)

Biomass is a renewable energy resource that can be converted into liquid fuel suitable for transportation applications and thus help meet the Energy Independence and Security Act renewable energy goals (U.S. Congress 2007). However, biomass is not always available in sufficient quantity at a price compatible with fuels production. Municipal solid waste (MSW) on the other hand is readily available in large quantities in some communities and is considered a partially renewable feedstock. Furthermore, MSW may be available for little or no cost. This report provides a techno-economic analysis of the production of mixed alcohols from MSW and compares it to the costs for a wood based plant. In this analysis, MSW is processed into refuse derived fuel (RDF) and then gasified in a plant co-located with a landfill. The resulting syngas is then catalytically converted to mixed alcohols. At a scale of 2000 metric tons per day of RDF, and using current technology, the minimum ethanol selling price at a 10% rate of return is approximately $1.85/gallon ethanol (early 2008 $). However, favorable economics are dependent upon the toxicity characteristics of the waste streams and that a market exists for the by-product scrap metal recovered from the RDF process.

Jones, Susanne B.; Zhu, Yunhua; Valkenburt, Corinne

2009-05-01T23:59:59.000Z

112

Aluminum Waste Reaction Indicators in a Municipal Solid Waste Landfill  

E-Print Network [OSTI]

Aluminum Waste Reaction Indicators in a Municipal Solid Waste Landfill Timothy D. Stark, F.ASCE1 landfills may contain aluminum from residential and commercial solid waste, industrial waste, and aluminum, may react with liquid in a landfill and cause uncontrolled temperature increases, significant changes

113

WASTE DESCRIPTION TYPE OF PROJECT POUNDS REDUCED,  

E-Print Network [OSTI]

/spills and subsequent clean up costs ($20,000) Sewage Sludge Volume Reduction 234,000 Radioactive Waste $910,000 $193,400 $716,600 60,000 gallons of radioactive STP liquid waste could have been disposed of through,000) Digital Imaging System Substitution 282 Hazardous Waste / Radioactive Waste / Industrial Waste $25,000 $25

114

Savannah River Site Achieves Transuranic Waste Disposition Goal...  

Office of Environmental Management (EM)

liquid waste contractor, Savannah River Remediation (SRR): Closed two more underground tanks containing radioactive waste, helping reduce a significant environmental risk to South...

115

Savannah River Site Waste Disposition Project  

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

Terrel J. Spears Terrel J. Spears Assistant Manager Waste Disposition Project DOE Savannah River Operations Office Savannah River Site Savannah River Site Waste Disposition Project Waste Disposition Project 2 Waste Disposition Project - Mission Radioactive Liquid Waste - Tank Waste Stabilization and Disposition - Disposition 36 million gallons of radioactive liquid waste - Close 49 underground storage tanks in which the waste now resides 3 36.7 Million 33.7 Mgal (92%) 3.0 Mgal (8%) Saltcake Sludge Salt Supernate Volume Curies 397 Million Curies (MCi) 212 MCi (54%) 185 MCi (46%) Gallons (Mgal) 36.5 Million 33.5 Mgal (92%) 3.0 Mgal (8%) Liquid Waste Background Liquid Waste Background * 2 tanks closed * 49 tanks remaining to close - aging, carbon steel - 27 compliant, 22 non-compliant - 12 have known leak sites

116

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

SciTech Connect (OSTI)

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

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

2012-08-29T23:59:59.000Z

117

Study on separation of platinum group metals from high level liquid waste using macroporous (MOTDGA-TOA)/SiO{sub 2}-P silica-based absorbent  

SciTech Connect (OSTI)

The recovery of platinum group metals (PGMs) from high level liquid waste (HLLW) by macroporous silica-based adsorbent, (MOTDGA-TOA)/SiO{sub 2}-P has been developed by impregnating two extractants of N,N'-dimethyl-N,N'-di-n-octyl-thio-diglycolamide (MOTDGA) and tri-n-octylamine (TOA) into a silica/polymer composite support (SiO{sub 2}-P). The adsorption of Ru(III), Rh(III) and Pd(II) have been investigated in simulated HLLW by batch method. The adsorbent has shown good uptake property for Pd(II). In addition, the combined use of MOTDGA and TOA improved the adsorption of Ru(III) and Rh(III) better than the individual use of them. The usability of adsorbent in radiation fields was further confirmed by irradiation experiments. The adsorbent remained to have the uptake capability for PGMs over the absorbed dose of 100 kGy, corresponding with one really adsorbed by the adsorbent, and showed good retention capability for Pd(II) even at the absorbed dose of 800 kGy. The chromatographic separation of metal ions was demonstrated with the adsorbent packed column, there is no influence of Re(VII) (instead of Tc) on the excellent separation behavior of Pd(II). (authors)

Ito, Tatsuya [Department of Quantum Science and Energy Engineering, Graduate School of Engineering, Tohoku University, Aoba 6-6, Aramaki, Aoba-ku, Sendai, Miyagi 980-8579 (Japan); Japan Atomic Energy Agency, Tokai-mura Naka-gun, Ibarak319-1195 (Japan); Kim, Seong-Yun; Xu, Yuanlai; Hitomi, Keitaro [Cyclotron and Radioisotope Center, Tohoku University, Aoba 6-3, Aramaki, Aoba-ku, Sendai, Miyagi 980-8578 (Japan); Ishii, Keizo [Department of Quantum Science and Energy Engineering, Graduate School of Engineering, Tohoku University, Aoba 6-6, Aramaki, Aoba-ku, Sendai, Miyagi 980-8579 (Japan); Nagaishi, Ryuji; Kimura, Takaumi [Japan Atomic Energy Agency, Tokai-mura Naka-gun, Ibarak319-1195 (Japan)

2013-07-01T23:59:59.000Z

118

Laboratory solvent reuse -- Liquid chromatography  

SciTech Connect (OSTI)

The objective of this work was to develop a method for reduction of waste solvent in the Process Engineering Chemistry Laboratory. The liquid chromatographs are the largest generators of explosive-contaminated waste in the laboratory. We developed a successful process for the reuse of solvents from the liquid chromatographs and demonstrated the utility of the process in the assay of hexanitrostilbene.

Quinlin, W.T.; Schaffer, C.L.

1992-11-01T23:59:59.000Z

119

SRS - Programs - Waste Solidification  

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

Waste Solidification Waste Solidification The two primary facilities operated within the Waste Solidification program are Saltstone and the Defense Waste Processing Facility (DWPF). Each DWPF canister is 10 feet tall and 2 feet in diameter, and typically takes a little over a day to fill. Each DWPF canister is 10 feet tall and 2 feet in diameter, and typically takes a little over a day to fill. The largest radioactive waste glassification plant in the world, DWPF converts the high-level liquid nuclear waste currently stored at the Savannah River Site (SRS) into a solid glass form suitable for long-term storage and disposal. Scientists have long considered this glassification process, called "vitrification," as the preferred option for immobilizing high-level radioactive liquids into a more stable, manageable form until a federal

120

Radioactive waste disposal package  

DOE Patents [OSTI]

A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

Lampe, Robert F. (Bethel Park, PA)

1986-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Radioactive Waste Radioactive Waste  

E-Print Network [OSTI]

#12;Radioactive Waste at UF Bldg 831 392-8400 #12;Radioactive Waste · Program is designed to;Radioactive Waste · Program requires · Generator support · Proper segregation · Packaging · labeling #12;Radioactive Waste · What is radioactive waste? · Anything that · Contains · or is contaminated

Slatton, Clint

122

Liquid heat capacity lasers  

DOE Patents [OSTI]

The heat capacity laser concept is extended to systems in which the heat capacity lasing media is a liquid. The laser active liquid is circulated from a reservoir (where the bulk of the media and hence waste heat resides) through a channel so configured for both optical pumping of the media for gain and for light amplification from the resulting gain.

Comaskey, Brian J. (Walnut Creek, CA); Scheibner, Karl F. (Tracy, CA); Ault, Earl R. (Livermore, CA)

2007-05-01T23:59:59.000Z

123

Waste-to-Energy Workshop  

Broader source: Energy.gov [DOE]

The Waste to Energy Roadmapping Workshop was held on November 5, 2014, in Arlington, Virginia. This workshop gathered waste-to-energy experts to identify the key technical barriers to the commercial deployment of liquid transportation fuels from wet waste feedstocks.

124

Basis for Section 3116 Determination for Salt Waste Disposal...  

Office of Environmental Management (EM)

gallons 1 2 (Mgal) of liquid radioactive waste stored in underground waste storage tanks at SRS. Much of this waste resulted from the reprocessing of spent nuclear fuel for...

125

Bubblers Speed Nuclear Waste Processing at SRS  

ScienceCinema (OSTI)

At the Department of Energy's Savannah River Site, American Recovery and Reinvestment Act funding has supported installation of bubbler technology and related enhancements in the Defense Waste Processing Facility (DWPF). The improvements will accelerate the processing of radioactive waste into a safe, stable form for storage and permit expedited closure of underground waste tanks holding 37 million gallons of liquid nuclear waste.

None

2014-08-06T23:59:59.000Z

126

Bubblers Speed Nuclear Waste Processing at SRS  

SciTech Connect (OSTI)

At the Department of Energy's Savannah River Site, American Recovery and Reinvestment Act funding has supported installation of bubbler technology and related enhancements in the Defense Waste Processing Facility (DWPF). The improvements will accelerate the processing of radioactive waste into a safe, stable form for storage and permit expedited closure of underground waste tanks holding 37 million gallons of liquid nuclear waste.

None

2010-11-14T23:59:59.000Z

127

Salt Waste Processing Initiatives  

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

Patricia Suggs Patricia Suggs Salt Processing Team Lead Assistant Manager for Waste Disposition Project Office of Environmental Management Savannah River Site Salt Waste Processing Initiatives 2 Overview * Current SRS Liquid Waste System status * Opportunity to accelerate salt processing - transformational technologies - Rotary Microfiltration (RMF) and Small Column Ion Exchange (SCIX) - Actinide Removal Process/Modular Caustic Side Solvent Extraction (ARP/MCU) extension with next generation extractant - Salt Waste Processing Facility (SWPF) performance enhancement - Saltstone enhancements * Life-cycle impacts and benefits 3 SRS Liquid Waste Total Volume >37 Million Gallons (Mgal) Total Curies 183 MCi (51% ) 175 MCi (49% ) >358 Million Curies (MCi) Sludge 34.3 Mgal (92% ) 3.0 Mgal (8%)

128

Waste Heat Boilers for Incineration Applications  

E-Print Network [OSTI]

Incineration is a widely used process for disposing of solid, liquid and gaseous wastes generated in various types of industries. In addition to destroying pollutants, energy may also be recovered from the waste gas streams in the form of steam...

Ganapathy, V.

129

Waste Management | Department of Energy  

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

Management Management Waste Management Nuclear Materials Disposition In fulfilling its mission, EM frequently manages and completes disposition of surplus nuclear materials and spent nuclear fuel. These are not waste. They are nuclear materials no longer needed for national security or other purposes, including spent nuclear fuel, special nuclear materials (as defined by the Atomic Energy Act) and other Nuclear Materials. Read more Tank Waste and Waste Processing The Department has approximately 88 million gallons of liquid waste stored in underground tanks and approximately 4,000 cubic meters of solid waste derived from the liquids stored in bins. The current DOE estimated cost for retrieval, treatment and disposal of this waste exceeds $50 billion to be spent over several decades.

130

Sorting and disposal of hazardous laboratory Radioactive waste  

E-Print Network [OSTI]

Sorting and disposal of hazardous laboratory waste Radioactive waste Solid radioactive waste or in a Perspex box. Liquid radioactive waste collect in a screw-cap plastic bottle, ½ or 1 L size. Place bottles in a tray to avoid spill Final disposal of both solid and radioactive waste into the yellow barrel

Maoz, Shahar

131

E-Print Network 3.0 - aqueous tank waste Sample Search Results  

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

Summary: by tank truck. The various wastes, when received, are pumped to storage tanks, then blended to produce... of Liquid Fluid Wastes General Description Light...

132

Tank Waste Committee Page 1  

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

immobilizing liquid and slurry waste. Steve said bulk vitrification has a TRL of five, meaning there have been lab experiments and a similar system has been validated in a relevant...

133

Salt Waste Processing Facility Fact Sheet | Department of Energy  

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

Services » Waste Management » Tank Waste and Waste Processing » Services » Waste Management » Tank Waste and Waste Processing » Salt Waste Processing Facility Fact Sheet Salt Waste Processing Facility Fact Sheet Nuclear material production operations at SRS resulted in the generation of liquid radioactive waste that is being stored, on an interim basis, in 49 underground waste storage tanks in the F- and H-Area Tank Farms. SWPF Fact Sheet More Documents & Publications EIS-0082-S2: Amended Record of Decision Savannah River Site Salt Waste Processing Facility Technology Readiness Assessment Report EIS-0082-S2: Record of Decision Waste Management Nuclear Materials & Waste Tank Waste and Waste Processing Waste Disposition Packaging and Transportation Site & Facility Restoration Deactivation & Decommissioning (D&D)

134

Waste Inspection Tomography (WIT)  

SciTech Connect (OSTI)

Waste Inspection Tomography (WIT) provides mobile semi-trailer mounted nondestructive examination (NDE) and assay (NDA) for nuclear waste drum characterization. WIT uses various computed tomography (CT) methods for both NDE and NDA of nuclear waste drums. Low level waste (LLW), transuranic (TRU), and mixed radioactive waste can be inspected and characterized without opening the drums. With externally transmitted x-ray NDE techniques, WIT has the ability to identify high density waste materials like heavy metals, define drum contents in two- and three-dimensional space, quantify free liquid volumes through density and x-ray attenuation coefficient discrimination, and measure drum wall thickness. With waste emitting gamma-ray NDA techniques, WIT can locate gamma emitting radioactive sources in two- and three-dimensional space, identify gamma emitting isotopic species, identify the external activity levels of emitting gamma-ray sources, correct for waste matrix attenuation, provide internal activity approximations, and provide the data needed for waste classification as LLW or TRU. The mobile feature of WIT allows inspection technologies to be brought to the nuclear waste drum storage site without the need to relocate drums for safe, rapid, and cost-effective characterization of regulated nuclear waste. The combination of these WIT characterization modalities provides the inspector with an unprecedented ability to non-invasively characterize the regulated contents of waste drums as large as 110 gallons, weighing up to 1,600 pounds. Any objects that fit within these size and weight restrictions can also be inspected on WIT, such as smaller waste bags and drums that are five and thirty-five gallons.

Bernardi, R.T.

1995-12-01T23:59:59.000Z

135

Test plan for evaluation of plasma melter technology for vitrification of high-sodium content low-level radioactive liquid wastes  

SciTech Connect (OSTI)

This document provides a test plan for the conduct of plasma arc vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. The vendor providing this test plan and conducting the work detailed within it [one of seven selected for glass melter testing under Purchase Order MMI-SVV-384212] is the Westinghouse Science and Technology Center (WSTC) in Pittsburgh, PA. WSTC authors of the test plan are D. F. McLaughlin, E. J. Lahoda, W. R. Gass, and N. D`Amico. The WSTC Program Manager for this test is D. F. McLaughlin. This test plan is for Phase I activities described in the above Purchase Order. Test conduct includes melting of glass frit with Hanford LLW Double-Shell Slurry Feed waste simulant in a plasma arc fired furnace.

McLaughlin, D.F.; Lahoda, E.J.; Gass, W.R.; D`Amico, N. [ed.

1994-10-20T23:59:59.000Z

136

Process removes Sr from nuclear wastes  

Science Journals Connector (OSTI)

Process removes Sr from nuclear wastes ... Scientists at Argonne National Laboratory have devised a chemical process for extracting and recovering strontium-90 from liquid nuclear wastes. ... Argonne chemist E. Philip Horwitz, head of the team, says it could be a significant aid in managing such radioactive wastes. ...

WARD WORTHY

1990-09-10T23:59:59.000Z

137

Enterprise Assessments Operational Awareness Record, Waste Treatment and Immobilization Plant December 2014  

Broader source: Energy.gov [DOE]

Operational Awareness Record for the Observation of Waste Treatment and Immobilization Plant High Level Waste Facility Radioactive Liquid Waste Disposal System Hazards Analysis Activities (EA-WTP-HLW-2014-08-18(a))

138

Shipment and Disposal of Solidified Organic Waste (Waste Type IV) to the Waste Isolation Pilot Plant (WIPP)  

SciTech Connect (OSTI)

In April of 2005, the last shipment of transuranic (TRU) waste from the Rocky Flats Environmental Technology Site to the WIPP was completed. With the completion of this shipment, all transuranic waste generated and stored at Rocky Flats was successfully removed from the site and shipped to and disposed of at the WIPP. Some of the last waste to be shipped and disposed of at the WIPP was waste consisting of solidified organic liquids that is identified as Waste Type IV in the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) document. Waste Type IV waste typically has a composition, and associated characteristics, that make it significantly more difficult to ship and dispose of than other Waste Types, especially with respect to gas generation. This paper provides an overview of the experience gained at Rocky Flats for management, transportation and disposal of Type IV waste at WIPP, particularly with respect to gas generation testing. (authors)

D'Amico, E. L [Washington TRU Solutions (United States); Edmiston, D. R. [John Hart and Associates (United States); O'Leary, G. A. [CH2M-WG Idaho, LLC (United States); Rivera, M. A. [Aspen Resources Ltd., Inc. (United States); Steward, D. M. [Boulder Research Enterprises, LLC (United States)

2006-07-01T23:59:59.000Z

139

NDAA Section 3116 Waste Determinations with Related Disposal...  

Office of Environmental Management (EM)

The other two DOE sites with similar waste (residuals remaining after cleaning out tanks and equipment that held liquid high-level waste) are Office of River Protection and...

140

Secondary Waste Forms and Technetium Management  

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

Secondary Waste Forms and Secondary Waste Forms and Technetium Management Joseph H. Westsik, Jr. Pacific Northwest National Laboratory EM HLW Corporate Board Meeting November 18, 2010 What are Secondary Wastes? Process condensates and scrubber and/or off-gas treatment liquids from the pretreatment and ILAW melter facilities at the Hanford WTP. Sent from WTP to the Effluent Treatment Facility (ETF) for treatment and disposal Treated liquid effluents under the ETF State Wastewater Discharge Permit Solidified liquid effluents under the Dangerous Waste Permit for disposal at the Integrated Disposal Facility (IDF) Solidification Treatment Unit to be added to ETF to provide capacity for WTP secondary liquid wastes 2 Evaporator Condensate Solution Evaporator Pretreatment Melter SBS/ WESP Secondary

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Investigation of the organic matter in inactive nuclear tank liquids  

SciTech Connect (OSTI)

Environmental Protection Agency (EPA) methodology for regulatory organics fails to account for the organic matter that is suggested by total organic carbon (TOC) analysis in the Oak Ridge National Laboratory (ORNL) inactive nuclear waste-tank liquids and sludges. Identification and measurement of the total organics are needed to select appropriate waste treatment technologies. An initial investigation was made of the nature of the organics in several waste-tank liquids. This report details the analysis of ORNL wastes.

Schenley, R.L.; Griest, W.H.

1990-08-01T23:59:59.000Z

142

The effect of concentration on the structure and crystallinity of a cementitious waste form for caustic wastes  

SciTech Connect (OSTI)

Cement-based waste forms have long been considered economical technologies for disposal of various types of waste. A solidified cementitious waste form, Cast Stone, was developed to immobilize the radioactive secondary waste from vitrification processes. In this work, Cast Stone was considered for a Na-based caustic liquid waste, and its physical properties were analyzed as a function of liquid waste loading up to 2 M Na. Differences in crystallinity (phase composition), microstructure, mesostructure (pore size distribution, surface area), and macrostructure (density, compressive strength) were investigated using various analytical techniques, in order to assess the suitability of Cast Stone as a chemically durable waste. It was found that the concentration of secondary waste simulant (caustic waste) had little effect on the relevant engineering properties of Cast Stone, showing that Cast Stone could be an effective and tolerant waste form for a wide range of concentrations of high sodium waste.

Chung, Chul-Woo; Turo, Laura A.; Ryan, Joseph V.; Johnson, Bradley R.; McCloy, John S.

2013-06-01T23:59:59.000Z

143

Nuclear Waste: Knowledge Waste?  

Science Journals Connector (OSTI)

...4). Although disposal of HLW remains...for long-term disposal is through deep...successful waste-disposal program has eluded...geologic repository at Yucca Mountain, Nevada. Authorized...Administration withdrew funding for Yucca Mountain...

Eugene A. Rosa; Seth P. Tuler; Baruch Fischhoff; Thomas Webler; Sharon M. Friedman; Richard E. Sclove; Kristin Shrader-Frechette; Mary R. English; Roger E. Kasperson; Robert L. Goble; Thomas M. Leschine; William Freudenburg; Caron Chess; Charles Perrow; Kai Erikson; James F. Short

2010-08-13T23:59:59.000Z

144

Hanford Tank Waste - Near Source Treatment of Low Activity Waste  

SciTech Connect (OSTI)

Treatment and disposition of Hanford Site waste as currently planned consists of I 00+ 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 ofthis 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 ofthe 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.

Ramsey, William Gene

2013-08-15T23:59:59.000Z

145

Lab optimizes burning of hazardous wastes  

Science Journals Connector (OSTI)

A new thermal destruction laboratory has gone into operation at Midwest Research Institute, Kansas City, Mo. The bench-scale facility, which can accommodate gram quantities of hazardous wastes in liquid, slurry, or solid forms, is used to determine ...

WARD WORTHY

1981-08-31T23:59:59.000Z

146

Estimating Waste Inventory and Waste Tank Characterization |...  

Office of Environmental Management (EM)

Estimating Waste Inventory and Waste Tank Characterization Estimating Waste Inventory and Waste Tank Characterization Summary Notes from 28 May 2008 Generic Technical Issue...

147

Nuclear Waste: Knowledge Waste?  

Science Journals Connector (OSTI)

...06520, USA. Nuclear power is re-emerging...proclaiming a nuclear renaissance...example, plant safety...liabilities, terrorism at plants and in transport...high-level nuclear wastes (HLW...factor in risk perceptions...supporting nuclear power in the abstract...

Eugene A. Rosa; Seth P. Tuler; Baruch Fischhoff; Thomas Webler; Sharon M. Friedman; Richard E. Sclove; Kristin Shrader-Frechette; Mary R. English; Roger E. Kasperson; Robert L. Goble; Thomas M. Leschine; William Freudenburg; Caron Chess; Charles Perrow; Kai Erikson; James F. Short

2010-08-13T23:59:59.000Z

148

Radiation Chemistry of Ionic Liquids  

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

Liquids Liquids James F. Wishart, Alison M. Funston, and Tomasz Szreder in "Molten Salts XIV" Mantz, R. A., et al., Eds.; The Electrochemical Society, Pennington, NJ, (2006) pp. 802-813. [Information about the volume (look just above this link)] Abstract: Ionic liquids have potentially important applications in nuclear fuel and waste processing, energy production, improving the efficiency and safety of industrial chemical processes, and pollution prevention. Successful use of ionic liquids in radiation-filled environments will require an understanding of ionic liquid radiation chemistry. For example, characterizing the primary steps of ionic liquid radiolysis will reveal radiolytic degradation pathways and suggest ways to prevent them or mitigate their effects on the properties of the material

149

Waste Treatment Plant - 12508  

SciTech Connect (OSTI)

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)

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

2012-07-01T23:59:59.000Z

150

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

SciTech Connect (OSTI)

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

Rogers, B.; Loveland, K.

2003-02-27T23:59:59.000Z

151

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

SciTech Connect (OSTI)

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

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

1994-01-01T23:59:59.000Z

152

Process for removing sulfate anions from waste water  

DOE Patents [OSTI]

A liquid emulsion membrane process for removing sulfate anions from waste water is disclosed. The liquid emulsion membrane process includes the steps of: (a) providing a liquid emulsion formed from an aqueous strip solution and an organic phase that contains an extractant capable of removing sulfate anions from waste water; (b) dispersing the liquid emulsion in globule form into a quantity of waste water containing sulfate anions to allow the organic phase in each globule of the emulsion to extract and absorb sulfate anions from the waste water and (c) separating the emulsion including its organic phase and absorbed sulfate anions from the waste water to provide waste water containing substantially no sulfate anions.

Nilsen, David N. (Lebanon, OR); Galvan, Gloria J. (Albany, OR); Hundley, Gary L. (Corvallis, OR); Wright, John B. (Albany, OR)

1997-01-01T23:59:59.000Z

153

Estimating heat of combustion for waste materials  

SciTech Connect (OSTI)

Describes a method of estimating the heat of combustion of hydrocarbon waste (containing S,N,Q,C1) in various physical forms (vapor, liquid, solid, or mixtures) when the composition of the waste stream is known or can be estimated. Presents an equation for predicting the heat of combustion of hydrocarbons containing some sulfur. Shows how the method is convenient for estimating the heat of combustion of a waste profile as shown in a sample calculation.

Chang, Y.C.

1982-11-01T23:59:59.000Z

154

Removal of radioactive and other hazardous material from fluid waste  

DOE Patents [OSTI]

Hollow glass microspheres obtained from fly ash (cenospheres) are impregnated with extractants/ion-exchangers and used to remove hazardous material from fluid waste. In a preferred embodiment the microsphere material is loaded with ammonium molybdophosphonate (AMP) and used to remove radioactive ions, such as cesium-137, from acidic liquid wastes. In another preferred embodiment, the microsphere material is loaded with octyl(phenyl)-N-N-diisobutyl-carbamoylmethylphosphine oxide (CMPO) and used to remove americium and plutonium from acidic liquid wastes.

Tranter, Troy J. (Idaho Falls, ID); Knecht, Dieter A. (Idaho Falls, ID); Todd, Terry A. (Aberdeen, ID); Burchfield, Larry A. (W. Richland, WA); Anshits, Alexander G. (Krasnoyarsk, RU); Vereshchagina, Tatiana (Krasnoyarsk, RU); Tretyakov, Alexander A. (Zheleznogorsk, RU); Aloy, Albert S. (St. Petersburg, RU); Sapozhnikova, Natalia V. (St. Petersburg, RU)

2006-10-03T23:59:59.000Z

155

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

SciTech Connect (OSTI)

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.

Jacobsen, P.H.

1997-09-23T23:59:59.000Z

156

Revision 08 (08/10) Form G Radioactive Waste Disposal Form  

E-Print Network [OSTI]

Revision 08 (08/10) Form G Radioactive Waste Disposal Form RS - 19g Proc. 9290, 9501 General Instructions: 1. Do not mix different waste forms together. Keep dry, liquid, and scintillation vials separate. 2. Do not mix waste of different isotopes. 3. Entries are to be made on this form each time waste

Nair, Sankar

157

Synthesis of three advanced biofuels from ionic liquid-pretreated switchgrass using engineered Escherichia coli  

Science Journals Connector (OSTI)

...and yard waste, respectively...for yard waste control strain...pCellulose on plant biomass treated...liquid pre-treatment . Biofuel...Insights into plant cell wall degradation...bioenergy systems . Biofuels Bioprod...2010 ) An integrated catalytic approach...

Gregory Bokinsky; Pamela P. Peralta-Yahya; Anthe George; Bradley M. Holmes; Eric J. Steen; Jeffrey Dietrich; Taek Soon Lee; Danielle Tullman-Ercek; Christopher A. Voigt; Blake A. Simmons; Jay D. Keasling

2011-01-01T23:59:59.000Z

158

Hanford Site waste management and environmental restoration integration plan  

SciTech Connect (OSTI)

The Hanford Site Waste Management and Environmental Restoration Integration Plan'' describes major actions leading to waste disposal and site remediation. The primary purpose of this document is to provide a management tool for use by executives who need to quickly comprehend the waste management and environmental restoration programs. The Waste Management and Environmental Restoration Programs have been divided into missions. Waste Management consists of five missions: double-shell tank (DST) wastes; single-shell tank (SST) wastes (surveillance and interim storage, stabilization, and isolation); encapsulated cesium and strontium; solid wastes; and liquid effluents. Environmental Restoration consists of two missions: past practice units (PPU) (including characterization and assessment of SST wastes) and surplus facilities. For convenience, both aspects of SST wastes are discussed in one place. A general category of supporting activities is also included. 20 refs., 14 figs., 7 tabs.

Merrick, D.L.

1990-04-30T23:59:59.000Z

159

Waste-to-Energy Workshop Agenda  

Broader source: Energy.gov [DOE]

The Bioenergy Technologies Office (BETO) at the Department of Energy aims to identify and address key technical barriers to the commercial deployment of liquid transportation fuels from waste feedstocks. As a part of this effort, BETO is organizing a Waste-to-Energy Roadmapping workshop. Workshop participants will join facilitated breakout sessions to discuss anaerobic digestion, hydrothermal liquefaction, and other processes that make productive use of wastewater residuals, biosolids, foodstuffs, and organic municipal solid waste. These discussions will be synthesized and used in developing a waste-to-energy technology roadmap.

160

Method for solidification of radioactive and other hazardous waste  

DOE Patents [OSTI]

Solidification of liquid radioactive waste, and other hazardous wastes, is accomplished by the method of the invention by incorporating the waste into a porous glass crystalline molded block. The porous block is first loaded with the liquid waste and then dehydrated and exposed to thermal treatment at 50-1,000.degree. C. The porous glass crystalline molded block consists of glass crystalline hollow microspheres separated from fly ash (cenospheres), resulting from incineration of fossil plant coals. In a preferred embodiment, the porous glass crystalline blocks are formed from perforated cenospheres of grain size -400+50, wherein the selected cenospheres are consolidated into the porous molded block with a binder, such as liquid silicate glass. The porous blocks are then subjected to repeated cycles of saturating with liquid waste, and drying, and after the last cycle the blocks are subjected to calcination to transform the dried salts to more stable oxides. Radioactive liquid waste can be further stabilized in the porous blocks by coating the internal surface of the block with metal oxides prior to adding the liquid waste, and by coating the outside of the block with a low-melting glass or a ceramic after the waste is loaded into the block.

Anshits, Alexander G. (Krasnoyarsk, RU); Vereshchagina, Tatiana A. (Krasnoyarsk, RU); Voskresenskaya, Elena N. (Krasnoyarsk, RU); Kostin, Eduard M. (Zheleznogorsk, RU); Pavlov, Vyacheslav F. (Krasnoyarsk, RU); Revenko, Yurii A. (Zheleznogorsk, RU); Tretyakov, Alexander A. (Zheleznogorsk, RU); Sharonova, Olga M. (Krasnoyarsk, RU); Aloy, Albert S. (Saint-Petersburg, RU); Sapozhnikova, Natalia V. (Saint-Petersburg, RU); Knecht, Dieter A. (Idaho Falls, ID); Tranter, Troy J. (Idaho Falls, ID); Macheret, Yevgeny (Idaho Falls, ID)

2002-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Investigation of the organic matter in inactive nuclear tank liquids. Environmental Restoration Program  

SciTech Connect (OSTI)

Environmental Protection Agency (EPA) methodology for regulatory organics fails to account for the organic matter that is suggested by total organic carbon (TOC) analysis in the Oak Ridge National Laboratory (ORNL) inactive nuclear waste-tank liquids and sludges. Identification and measurement of the total organics are needed to select appropriate waste treatment technologies. An initial investigation was made of the nature of the organics in several waste-tank liquids. This report details the analysis of ORNL wastes.

Schenley, R.L.; Griest, W.H.

1990-08-01T23:59:59.000Z

162

E-Print Network 3.0 - acid liquid radioactive Sample Search Results  

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

WASHINGTON, D.C. 20460 Summary: radioactive wastes in liquid or solid forms. Oil and gas production, as an example, also results... a radioactive source, plus radioactive...

163

A Case for Molecular Recognition in Nuclear Separations: Sulfate Separation from Nuclear Wastes  

Science Journals Connector (OSTI)

In this paper, we present the case for molecular-recognition approaches for sulfate removal from radioactive wastes via the use of anion-sequestering systems selective for sulfate, using either liquidliquid extraction or crystallization. Potential ...

Bruce A. Moyer; Radu Custelcean; Benjamin P. Hay; Jonathan L. Sessler; Kristin Bowman-James; Victor W. Day; Sung-Ok Kang

2012-11-07T23:59:59.000Z

164

Quality Assurance Program Plan (QAPP) Waste Management Project  

SciTech Connect (OSTI)

This document is the Quality Assurance Program Plan (QAPP) for Waste Management Federal Services of Hanford, Inc. (WMH), that implements the requirements of the Project Hanford Management Contract (PHMC), HNF-MP-599, Project Hanford Quality Assurance Program Description (QAPD) document, and the Hanford Federal Facility Agreement with Consent Order (Tri-Party Agreement), Sections 6.5 and 7.8. WHM is responsible for the treatment, storage, and disposal of liquid and solid wastes generated at the Hanford Site as well as those wastes received from other US Department of Energy (DOE) and non-DOE sites. WMH operations include the Low-Level Burial Grounds, Central Waste Complex (a mixed-waste storage complex), a nonradioactive dangerous waste storage facility, the Transuranic Storage Facility, T Plant, Waste Receiving and Processing Facility, 200 Area Liquid Effluent Facility, 200 Area Treated Effluent Disposal Facility, the Liquid Effluent Retention Facility, the 242-A Evaporator, 300 Area Treatment Effluent Disposal Facility, the 340 Facility (a radioactive liquid waste handling facility), 222-S Laboratory, the Waste Sampling and Characterization Facility, and the Hanford TRU Waste Program.

VOLKMAN, D.D.

1999-10-27T23:59:59.000Z

165

TRU waste-sampling program  

SciTech Connect (OSTI)

As part of a TRU waste-sampling program, Los Alamos National Laboratory retrieved and examined 44 drums of /sup 238/Pu- and /sup 239/Pu-contaminated waste. The drums ranged in age from 8 months to 9 years. The majority of drums were tested for pressure, and gas samples withdrawn from the drums were analyzed by a mass spectrometer. Real-time radiography and visual examination were used to determine both void volumes and waste content. Drum walls were measured for deterioration, and selected drum contents were reassayed for comparison with original assays and WIPP criteria. Each drum tested at atmospheric pressure. Mass spectrometry revealed no problem with /sup 239/Pu-contaminated waste, but three 8-month-old drums of /sup 238/Pu-contaminated waste contained a potentially hazardous gas mixture. Void volumes fell within the 81 to 97% range. Measurements of drum walls showed no significant corrosion or deterioration. All reassayed contents were within WIPP waste acceptance criteria. Five of the drums opened and examined (15%) could not be certified as packaged. Three contained free liquids, one had corrosive materials, and one had too much unstabilized particulate. Eleven drums had the wrong (or not the most appropriate) waste code. In many cases, disposal volumes had been inefficiently used. 2 refs., 23 figs., 7 tabs.

Warren, J.L.; Zerwekh, A.

1985-08-01T23:59:59.000Z

166

Categorical Exclusion 4565, Waste Management Construction Support  

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

FornI FornI Project Title: Waste Management Construction Support (4565) Program or Program Office: Y -12 Site Office Location: Oak Ridge Tennessee Project Description: This work scope is an attempt to cover the general activities that construction would perform in support of Waste Management activities. Work includes construction work performed in support of Waste Management Sustainability and Stewardship projects and programs to include: load waste into containers; open, manipulate containers; empty containers; decommission out-of-service equipment (includes removal of liquids, hazardous, and universal wastes); apply fabric and gravel to ground; transport equipment; transport materials; transport waste; remove vegetation; place barriers; place erosion controls; operate wheeled and tracked equipment; general carpentry. Work will be performed on dirt, vegetated, graveled, or paved surfaces in

167

Thermal Pretreatment For TRU Waste Sorting  

SciTech Connect (OSTI)

Japan Atomic Energy Agency conducted a study on thermal treatment of TRU waste to develop a removal technology for materials that are forbidden for disposal. The thermal pretreatment in which hot nitrogen and/or air is introduced to the waste is a process of removing combustibles, liquids, and low melting point metals from PVC wrapped TRU waste. In this study, thermal pretreatment of simulated waste was conducted using a desktop thermal treatment vessel and a laboratory scale thermal pretreatment system. Combustibles and low melting point metals are effectively separated from wastes by choosing appropriate temperature of flowing gases. Combustibles such as papers, PVC, oil, etc. were removed and low melting point metals such as zinc, lead, and aluminum were separated from the simulated waste by the thermal pretreatment. (authors)

Sasaki, T.; Aoyama, Y.; Miyamoto, Y.; Yamaguchi, H. [Japan Atomic Energy Agency, Tokai-mura, Ibaraki (Japan)

2008-07-01T23:59:59.000Z

168

CONCEPTUAL DATA MODELING OF THE INTEGRATED DATABASE FOR THE RADIOACTIVE WASTE MANAGEMENT  

SciTech Connect (OSTI)

A study of a database system that can manage radioactive waste collectively on a network has been carried out. A conceptual data modeling that is based on the theory of information engineering (IE), which is the first step of the whole database development, has been studied to manage effectively information and data related to radioactive waste. In order to establish the scope of the database, user requirements and system configuration for radioactive waste management were analyzed. The major information extracted from user requirements are solid waste, liquid waste, gaseous waste, and waste related to spent fuel. The radioactive waste management system is planning to share information with associated companies.

Park, H.S; Shon, J.S; Kim, K.J; Park, J.H; Hong, K.P; Park, S.H

2003-02-27T23:59:59.000Z

169

Microsoft PowerPoint - S05-05_Zapp_Liquid Air Interface.ppt  

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

Liquid-Air Interface Corrosion Studies at SRS Liquid-Air Interface Corrosion Studies at SRS EM Waste Processing Technical Exchange 2010 Philip E. Zapp Savannah River National Laboratory November 17, 2010 SRNL-STI-2010-00695 Print Close 2 Liquid-Air Interface Corrosion Studies at SRS SRNL-STI-2010-00695 Introduction Pitting Corrosion in Carbon Steel Waste Tanks Pitting Induced by Dilute Waste Solutions Dilution for feed preparation for vitrification; waste removal Focus: Pitting Susceptibility at Liquid-Air Interface Service Experience Hydroxide Depletion Model Type III tanks under constr. Tank with ventilation & cooling equip. Print Close 3 Liquid-Air Interface Corrosion Studies at SRS SRNL-STI-2010-00695 Background Pitting in carbon steel at and above liquid-air interface in dilute wastes ([Nitrate] < 1 M)

170

Method for stabilizing low-level mixed wastes at room temperature  

DOE Patents [OSTI]

A method to stabilize solid and liquid waste at room temperature is provided comprising combining solid waste with a starter oxide to obtain a powder, contacting the powder with an acid solution to create a slurry, said acid solution containing the liquid waste, shaping the now-mixed slurry into a predetermined form, and allowing the now-formed slurry to set. The invention also provides for a method to encapsulate and stabilize waste containing cesium comprising combining the waste with Zr(OH){sub 4} to create a solid-phase mixture, mixing phosphoric acid with the solid-phase mixture to create a slurry, subjecting the slurry to pressure; and allowing the now pressurized slurry to set. Lastly, the invention provides for a method to stabilize liquid waste, comprising supplying a powder containing magnesium, sodium and phosphate in predetermined proportions, mixing said powder with the liquid waste, such as tritium, and allowing the resulting slurry to set. 4 figs.

Wagh, A.S.; Singh, D.

1997-07-08T23:59:59.000Z

171

Method for stabilizing low-level mixed wastes at room temperature  

DOE Patents [OSTI]

A method to stabilize solid and liquid waste at room temperature is provided comprising combining solid waste with a starter oxide to obtain a powder, contacting the powder with an acid solution to create a slurry, said acid solution containing the liquid waste, shaping the now-mixed slurry into a predetermined form, and allowing the now-formed slurry to set. The invention also provides for a method to encapsulate and stabilize waste containing cesium comprising combining the waste with Zr(OH).sub.4 to create a solid-phase mixture, mixing phosphoric acid with the solid-phase mixture to create a slurry, subjecting the slurry to pressure; and allowing the now pressurized slurry to set. Lastly, the invention provides for a method to stabilize liquid waste, comprising supplying a powder containing magnesium, sodium and phosphate in predetermined proportions, mixing said powder with the liquid waste, such as tritium, and allowing the resulting slurry to set.

Wagh, Arun S. (Joliet, IL); Singh, Dileep (Westmont, IL)

1997-01-01T23:59:59.000Z

172

Integrated plant for treatment of liquid radwaste  

SciTech Connect (OSTI)

In the early 1980`s, AECL Research, at its Chalk River Laboratories (CRL) site, built a Waste Treatment Centre for managing low-level radioactive aqueous liquid wastes. At present, two industrial liquid waste streams are being routinely treated. One stream originates from the central Decontamination Centre (DC), where reactor components, protective plastic clothing, and respirators are cleaned. The other Active Drain (AD) stream is produced from a large and diverse number of research laboratories and radioisotope production facilities. The two waste streams, totalling about 2500 m per year (0.66 million US gallons), are volume reduced by a combination of continuous crossflow microfiltration (MF), spiral wound reverse osmosis (SWRO), and tubular reverse osmosis (TRO) membrane technologies; two thin-film evaporators (TFE) are employed for (i) the final volume reduction step, and (ii) the subsequent solidification of evaporator bottom with bitumen for containment of the radioactivity.

Sen Gupta, S.K. [Chalk River Laboratories, Ontario (Canada)

1995-05-01T23:59:59.000Z

173

liquids | EMSL  

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

leads are available at this time. Iodine Solubility in Low-Activity Waste Borosilicate Glass at 1000 C. Abstract: The purpose of this study was to determine the solubility of...

174

Utilization of waste heat stream in distillation  

SciTech Connect (OSTI)

Cost of separation can be reduced by utilizing all available energy streams at various temperature levels. In the simplest case a waste energy heat stream can be used to partially vaporize a liquid feed stream. A more beneficial process involves an entire evaporation of a portion of the feed and introducing it into a column below the liquid portion of the feed. One can also use the waste energy stream as a heating medium in an intermediate reboiler in the column. There is, however, a limit to the amount of the waste energy that can be utilized in each case, beyond which this approach is no longer beneficial. Detailed analysis of the waste heat utilization enables one to determine this limit and compare each of these flowsheet options.

Fidkowski, Z.T.; Agrawal, R. [Air Products and Chemicals, Inc., Allentown, PA (United States)

1995-04-01T23:59:59.000Z

175

Department of Energy Issues Final Request for Proposals for Savannah River  

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

Final Request for Proposals for Final Request for Proposals for Savannah River Site Liquid Waste Contract Department of Energy Issues Final Request for Proposals for Savannah River Site Liquid Waste Contract September 13, 2007 - 2:33pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced the release of a final Request for Proposals (RFP) for the competitive selection of a Liquid Waste (LW) contractor for the Savannah River Site (SRS). The resulting contract is expected to be approximately $3 billion over six years with an option for a two year extension. The fee for the LW contract is up to ten percent. The primary facilities related to this procurement include liquid radioactive waste tank farms, the Defense Waste Processing Facility, the saltstone facility, and potential operation of the Salt Waste Processing

176

Department of Energy Issues Final Request for Proposals for Savannah River  

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

Issues Final Request for Proposals for Issues Final Request for Proposals for Savannah River Site Liquid Waste Contract Department of Energy Issues Final Request for Proposals for Savannah River Site Liquid Waste Contract September 13, 2007 - 2:33pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced the release of a final Request for Proposals (RFP) for the competitive selection of a Liquid Waste (LW) contractor for the Savannah River Site (SRS). The resulting contract is expected to be approximately $3 billion over six years with an option for a two year extension. The fee for the LW contract is up to ten percent. The primary facilities related to this procurement include liquid radioactive waste tank farms, the Defense Waste Processing Facility, the saltstone facility, and potential operation of the Salt Waste Processing

177

Waste Hoist  

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

Primary Hoist: 45-ton Rope-Guide Friction Hoist Completely enclosed (for contamination control), the waste hoist at WIPP is a modern friction hoist with rope guides. With a 45-ton...

178

Nuclear Waste  

Science Journals Connector (OSTI)

Nuclear waste is radioactive material no longer considered valuable...238U, 235U, and 226Ra (where the latter decays to 222Rn gas by emitting an alpha particle) or formed through fission of fissile radioisotopes ...

Rob P. Rechard

2014-01-01T23:59:59.000Z

179

Recycling of CdTe photovoltaic waste  

DOE Patents [OSTI]

A method for extracting and reclaiming metals from scrap CdTe photovoltaic cells and manufacturing waste by leaching the waste with a leaching solution comprising nitric acid and water, skimming any plastic material from the top of the leaching solution, separating the glass substrate from the liquid leachate and electrolyzing the leachate to separate Cd from Te, wherein the Te is deposits onto a cathode while the Cd remains in solution.

Goozner, Robert E. (Charlotte, NC); Long, Mark O. (Charlotte, NC); Drinkard, Jr., William F. (Charlotte, NC)

1999-01-01T23:59:59.000Z

180

H-Tank Farm Waste Determination | Department of Energy  

Office of Environmental Management (EM)

(SRS) in South Carolina to complete cleanup and closure of the underground liquid waste tanks in the H Tank Farm as they are emptied and cleaned. The action marked a major...

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Office of Enterprise Assessments Review of the Hanford Site Waste...  

Energy Savers [EERE]

of liquid or semi-solid radioactive and chemical waste stored in 177 underground tanks at the Hanford Site. ORP serves as DOE line management for two functions: the Tank...

182

Independent Oversight Review of the Hanford Site Waste Treatment...  

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

of liquid or semi-solid radioactive and chemical waste stored in 177 underground tanks at the Hanford Site. ORP serves as DOE line management for two functions: the Tank...

183

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

Office of Environmental Management (EM)

is designed to treat 900,000 gallons of radioactive liquid waste stored in underground tanks at a former Cold War spent nuclear fuel reprocessing facility located at DOE's Idaho...

184

Drilling Waste Management Fact Sheet: Slurry Injection of Drilling Wastes  

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

Slurry Injection Slurry Injection Fact Sheet - Slurry Injection of Drilling Wastes Underground Injection of Drilling Wastes Several different approaches are used for injecting drilling wastes into underground formations for permanent disposal. Salt caverns are described in a separate fact sheet. This fact sheet focuses on slurry injection technology, which involves grinding or processing solids into small particles, mixing them with water or some other liquid to make a slurry, and injecting the slurry into an underground formation at pressures high enough to fracture the rock. The process referred to here as slurry injection has been given other designations by different authors, including slurry fracture injection (this descriptive term is copyrighted by a company that provides slurry injection services), fracture slurry injection, drilled cuttings injection, cuttings reinjection, and grind and inject.

185

Tank Waste Corporate Board Meeting 11/06/08 | Department of Energy  

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

11/06/08 11/06/08 Tank Waste Corporate Board Meeting 11/06/08 The following documents are associated with the Tank Waste Corporate Board Meeting held on November 6th, 2008. Note: (Please contact Steven Ross at steven.ross@em.doe.gov for a HLW Glass Waste Loadings version with animations on slide 6). Slurry Retrieval, Pipeline Transport & Plugging and Mixing Workshop The Way Ahead - West Valley Demonstration Project High-Level Liquid Waste Tank Integrity Workshop - 2008 Savannah River Tank Waste Residuals Hanford Tank Waste Residuals HLW Glass Waste Loadings High-Level Waste Corporate Board Performance Assessment Subcommittee More Documents & Publications Tank Waste Corporate Board Meeting 11/18/10 System Planning for Low-Activity Waste at Hanford Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility

186

Chapter 30 Waste Management: General Administrative Procedures (Kentucky) |  

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

Chapter 30 Waste Management: General Administrative Procedures Chapter 30 Waste Management: General Administrative Procedures (Kentucky) Chapter 30 Waste Management: General Administrative Procedures (Kentucky) < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Retail Supplier Rural Electric Cooperative State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Solar Buying & Making Electricity Wind Program Info State Kentucky Program Type Environmental Regulations Provider Department for Environmental Protection The waste management administrative regulations apply to the disposal of solid waste and the management of all liquid, semisolid, solid, or gaseous

187

Characterization of industrial process waste heat and input heat streams  

SciTech Connect (OSTI)

The nature and extent of industrial waste heat associated with the manufacturing sector of the US economy are identified. Industry energy information is reviewed and the energy content in waste heat streams emanating from 108 energy-intensive industrial processes is estimated. Generic types of process equipment are identified and the energy content in gaseous, liquid, and steam waste streams emanating from this equipment is evaluated. Matchups between the energy content of waste heat streams and candidate uses are identified. The resultant matrix identifies 256 source/sink (waste heat/candidate input heat) temperature combinations. (MHR)

Wilfert, G.L.; Huber, H.B.; Dodge, R.E.; Garrett-Price, B.A.; Fassbender, L.L.; Griffin, E.A.; Brown, D.R.; Moore, N.L.

1984-05-01T23:59:59.000Z

188

WASTE TO WATTS Waste is a Resource!  

E-Print Network [OSTI]

WASTE TO WATTS Waste is a Resource! energy forum Case Studies from Estonia, Switzerland, Germany Bossart,· ABB Waste-to-Energy Plants Edmund Fleck,· ESWET Marcel van Berlo,· Afval Energie Bedrijf From Waste to Energy To Energy from Waste #12;9.00-9.30: Registration 9.30-9.40: Chairman Ella Stengler opens

Columbia University

189

Mixed waste disposal facilities at the Savannah River Site  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE's Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site's waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission.

Wells, M.N.; Bailey, L.L.

1991-01-01T23:59:59.000Z

190

Mixed waste disposal facilities at the Savannah River Site  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE`s Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site`s waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission.

Wells, M.N.; Bailey, L.L.

1991-12-31T23:59:59.000Z

191

November 8, 1983: Defense Waste Processing Facility | Department of Energy  

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

November 8, 1983: Defense Waste Processing Facility November 8, 1983: Defense Waste Processing Facility November 8, 1983: Defense Waste Processing Facility November 8, 1983: Defense Waste Processing Facility November 8, 1983 The Department begins construction of the Defense Waste Processing Facility (DWPF) at the Savannah River Plant in South Carolina. DWPF is designed to make high-level nuclear waste into a glass-like substance, which will then be shipped to a repository. DWPF will mix borosilicate glass with the waste, heat it to 2000 degrees F, and pour the mixture into stainless steel canisters. The mixture will cool into solid glass that can be permanently stored. DWPF will immobilize the more than 34 million gallons of liquid high-level waste that have accumulated from producing defense-related nuclear materials

192

Solid Waste Program (Alabama) | Department of Energy  

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

Program (Alabama) Program (Alabama) Solid Waste Program (Alabama) < Back Eligibility Commercial Construction Developer General Public/Consumer Industrial Residential Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Alabama Program Type Environmental Regulations This article states the authority of the department, regulations for the control of unauthorized dumping, disposal fees, violations and penalties. Solid waste refers to any garbage, rubbish, construction or demolition debris, ash, or sludge from a waste treatment facility, water supply plant, or air pollution control facility, and any other discarded materials, including solid, liquid, semisolid, or contained gaseous material resulting

193

Waste management project fiscal year 1998 multi-year work plan WBS 1.2  

SciTech Connect (OSTI)

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.

Slaybaugh, R.R.

1997-08-29T23:59:59.000Z

194

Savannah River Site sample and analysis plan for Clemson Technical Center waste  

SciTech Connect (OSTI)

The purpose of this sampling and analysis plan is to determine the chemical, physical and radiological properties of the SRS radioactive Polychlorinated Biphenyl (PCB) liquid waste stream, to verify that it conforms to Waste Acceptance Criteria of the Department of Energy (DOE) East Tennessee Technology Park (ETTP) Toxic Substance Control Act (TSCA) Incineration Facility. Waste being sent to the ETTP TSCA Incinerator for treatment must be sufficiently characterized to ensure that the waste stream meets the waste acceptance criteria to ensure proper handling, classification, and processing of incoming waste to meet the Waste Storage and Treatment Facility`s Operating Permits. This sampling and analysis plan is limited to WSRC container(s) of homogeneous or multiphasic radioactive PCB contaminated liquids generated in association with a treatability study at Clemson Technical Center (CTC) and currently stored at the WSRC Solid Waste Division Mixed Waste Storage Facility (MWSF).

Hagstrom, T.

1998-04-01T23:59:59.000Z

195

Aluminum Reactions and Problems in Municipal Solid Waste Landfills  

E-Print Network [OSTI]

Aluminum Reactions and Problems in Municipal Solid Waste Landfills G. Vincent Calder, Ph.D.1 ; and Timothy D. Stark, Ph.D., P.E., F.ASCE2 Abstract: Aluminum enters municipal solid waste MSW landfills from problematic for landfill operations by generating undesirable heat, liquid leachate, and gases

196

DWPF waste form compliance plan (Draft Revision)  

SciTech Connect (OSTI)

The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970`s, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in December, 1982) on the waste form. The Department of Energy, recognizing that start-up of the DWPF would considerably precede licensing of a repository, instituted a Waste Acceptance Process to ensure that these canistered waste forms would be acceptable for eventual disposal at a federal repository. This report is a revision of the DWPF compliance plan.

Plodinec, M.J.; Marra, S.L.

1991-12-31T23:59:59.000Z

197

DWPF waste form compliance plan (Draft Revision)  

SciTech Connect (OSTI)

The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970's, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in December, 1982) on the waste form. The Department of Energy, recognizing that start-up of the DWPF would considerably precede licensing of a repository, instituted a Waste Acceptance Process to ensure that these canistered waste forms would be acceptable for eventual disposal at a federal repository. This report is a revision of the DWPF compliance plan.

Plodinec, M.J.; Marra, S.L.

1991-01-01T23:59:59.000Z

198

LNG liquid-liquid immiscibility  

SciTech Connect (OSTI)

Although natural gas species rarely exhibit liquid-liquid immiscibility in binary systems, the presence of additional components can extend the domain of immiscibility in those few binary systems where it already exists or produce immiscibility in binary systems where it had not existed. If the solute has the proper molecular relation to the solvent mixture background, liquid-liquid-vapor (LLV) behavior will occur; such phenomena greatly complicate the design of LNG processing equipment. To aid LNG engineers, researchers mapped the thermodynamic behavior of four ternary LLV systems and examined the effects of the second solvents - ethane, propane, n-butane, and CO/sub 2/ - on the binary methane + n-octane system.

Luks, K.D.; Kohn, J.P.

1981-09-01T23:59:59.000Z

199

EIS-0063: Waste Management Operations, Double-Shell Tanks for Defense High Level Radioactive Waste Storage, Hanford Site, Richland, Washington  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy developed this statement to evaluate the existing tank design and consider additional specific design and safety feature alternatives for the thirteen tanks being constructed for storage of defense high-level radioactive liquid waste at the Hanford Site in Richland, Washington. This statement supplements ERDA-1538, "Final Environmental Statement on Waste Management Operation."

200

Waste Disposal (Illinois)  

Broader source: Energy.gov [DOE]

This article lays an outline of waste disposal regulations, permits and fees, hazardous waste management and underground storage tank requirements.

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Waste minimization/pollution prevention study of high-priority waste streams  

SciTech Connect (OSTI)

Although waste minimization has been practiced by the Metals and Ceramics (M&C) Division in the past, the effort has not been uniform or formalized. To establish the groundwork for continuous improvement, the Division Director initiated a more formalized waste minimization and pollution prevention program. Formalization of the division`s pollution prevention efforts in fiscal year (FY) 1993 was initiated by a more concerted effort to determine the status of waste generation from division activities. The goal for this effort was to reduce or minimize the wastes identified as having the greatest impact on human health, the environment, and costs. Two broad categories of division wastes were identified as solid/liquid wastes and those relating to energy use (primarily electricity and steam). This report presents information on the nonradioactive solid and liquid wastes generated by division activities. More specifically, the information presented was generated by teams of M&C staff members empowered by the Division Director to study specific waste streams.

Ogle, R.B. [comp.

1994-03-01T23:59:59.000Z

202

Idaho National Engineering Laboratory nonradiological waste management information for 1994 and record to date  

SciTech Connect (OSTI)

This document provides detailed data and graphics on airborne and liquid effluent releases, fuel oil and coal consumption, water usage, and hazardous and mixed waste generated for calendar year 1994. This report summarizes industrial waste data records compiled since 1971 for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Nonradiological Waste Management Information System.

French, D.L.; Lisee, D.J.; Taylor, K.A.

1995-08-01T23:59:59.000Z

203

Idaho National Engineering Laboratory Nonradiological Waste Management Information for 1992 and record to date  

SciTech Connect (OSTI)

This document provides detailed data and graphics on airborne and liquid effluent releases, fuel oil and coal consumption, water usage, and hazardous and mixed waste generated for calendar year 1992. This report summarizes industrial waste data records compiled since 1971 for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Nonradiological Waste Management Information System.

Randall, V.C.; Sims, A.M.

1993-08-01T23:59:59.000Z

204

Idaho National Engineering Laboratory Nonradiological Waste Management Information for 1993 and record to date  

SciTech Connect (OSTI)

This document provides detailed data and graphics on airborne and liquid effluent releases, fuel oil and coal consumption, water usage, and hazardous and mixed waste generated for calendar year 1993. This report summarizes industrial waste data records compiled since 1971 for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Nonradiological Waste Management Information System.

Sims, A.M.; Taylor, K.A.

1994-08-01T23:59:59.000Z

205

Waste Treatment and Immobilation Plant HLW Waste Vitrification...  

Office of Environmental Management (EM)

Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility Full Document and Summary Versions...

206

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE  

E-Print Network [OSTI]

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE January 2010 Prepared for the Interagency left intentionally blank.] #12;Prepared for the U.S. Department of Energy PNNL-SA-69994 under Contract DE-AC05-76RL01830 Waste Disposal Workshops: Anthrax-Contaminated Waste AM Lesperance JF Upton SL

207

Hanford Waste Physical and Rheological Properties: Data and Gaps  

SciTech Connect (OSTI)

The Hanford Site in Washington State manages 177 underground storage tanks containing approximately 250,000 m3 of waste generated during past defense reprocessing and waste management operations. These tanks contain a mixture of sludge, saltcake and supernatant liquids. The insoluble sludge fraction of the waste consists of metal oxides and hydroxides and contains the bulk of many radionuclides such as the transuranic components and 90Sr. The saltcake, generated by extensive evaporation of aqueous solutions, consists primarily of dried sodium salts. The supernates consist of concentrated (5-15 M) aqueous solutions of sodium and potassium salts. The 177 storage tanks include 149 single-shell tanks (SSTs) and 28 double -hell tanks (DSTs). Ultimately the wastes need to be retrieved from the tanks for treatment and disposal. The SSTs contain minimal amounts of liquid wastes, and the Tank Operations Contractor is continuing a program of moving solid wastes from SSTs to interim storage in the DSTs. The Hanford DST system provides the staging location for waste feed delivery to the Department of Energy (DOE) Office of River Protections (ORP) Hanford Tank Waste Treatment and Immobilization Plant (WTP). The WTP is being designed and constructed to pretreat and then vitrify a large portion of the wastes in Hanfords 177 underground waste storage tanks.

Wells, Beric E.; Kurath, Dean E.; Mahoney, Lenna A.; Onishi, Yasuo; Huckaby, James L.; Cooley, Scott K.; Burns, Carolyn A.; Buck, Edgar C.; Tingey, Joel M.; Daniel, Richard C.; Anderson, K. K.

2011-08-01T23:59:59.000Z

208

NDAA Section 3116 Waste Determinations with Related Disposal Performance  

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

NDAA Section NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 authorizes the Secretary of Energy, in consultation with the Nuclear Regulatory Commission, to reclassify certain waste from reprocessing spent nuclear fuel from high-level waste to low-level waste if it meets the criteria set forth in Section 3116. Section 3116 is currently only applicable to Idaho National Laboratory (INL) and the Savannah River Site (SRS). The other two DOE sites with similar waste (residuals remaining after cleaning out tanks and equipment that held liquid high-level waste)

209

Oklahoma Hazardous Waste Management Act (Oklahoma) | Department of Energy  

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

Oklahoma Hazardous Waste Management Act (Oklahoma) Oklahoma Hazardous Waste Management Act (Oklahoma) Oklahoma Hazardous Waste Management Act (Oklahoma) < Back Eligibility Agricultural Construction Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Utility Program Info State Oklahoma Program Type Environmental Regulations Provider Oklahoma Department of Environmental Quality A hazardous waste facility permit from the Department of Environmental Quality is required to store, treat or dispose of hazardous waste materials, or to construct, own or operate any facility engaged in the operation of storing, treating or disposing of hazardous waste or storing recyclable materials. The Department shall not issue a permit for the treatment, disposal or temporary storage of any liquid hazardous waste in a

210

EIS-0217: Savannah River Site Waste Management | Department of Energy  

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

17: Savannah River Site Waste Management 17: Savannah River Site Waste Management EIS-0217: Savannah River Site Waste Management Summary This EIS evaluates the potential environmental impacts and costs of storing, treating, and/or disposing of liquid high-level radioactive, low-level radioactive, hazardous, mixed (radioactive and hazardous), and transuranic wastes at SRS. Public Comment Opportunities None available at this time. Documents Available for Download June 28, 2001 EIS-0217: Amended Record of Decision Savannah River Site Waste Management, Savannah River Operations Office, Aiken, South Carolina May 19, 1997 EIS-0217: Supplemental Record of Decision Savannah River Site Waste Management May 19, 1997 EIS-0217: Supplemental Record of Decision Savannah River Site Waste Management, Savannah River Operations Office,

211

Sodium-Bearing Waste Treatment Alternatives Implementation Study  

SciTech Connect (OSTI)

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).

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

2004-07-01T23:59:59.000Z

212

EIS-0287: Idaho High-Level Waste and Facilities Disposition Final  

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

Idaho High-Level Waste and Facilities Disposition Final Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) EIS-0287: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, DOE/EIS-0287 (September 2002)

213

EIS-0287: Idaho High-Level Waste & Facilities Disposition | Department of  

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

7: Idaho High-Level Waste & Facilities Disposition 7: Idaho High-Level Waste & Facilities Disposition EIS-0287: Idaho High-Level Waste & Facilities Disposition SUMMARY This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD January 12, 2010 EIS-0287: Amended Record of Decision Idaho High-Level Waste and Facilities Disposition January 4, 2010

214

Waste Processing | Department of Energy  

Office of Environmental Management (EM)

Processing Waste Processing Workers process and repackage waste at the Transuranic Waste Processing Centers Cask Processing Enclosure. Workers process and repackage waste at...

215

Waste Hoist  

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

Primary Hoist: 45-ton Rope-Guide Friction Hoist Largest friction hoist in the world when it was built in 1985 Completely enclosed (for contamination control), the waste hoist at WIPP is a modern friction hoist with rope guides (uses a balanced counterweight and tail ropes). With a 45-ton capacity, it was the largest friction hoist in the world when it was built in 1986. Hoist deck footprint: 2.87m wide x 4.67m long Hoist deck height: 2.87m wide x 7.46m high Access height to the waste hoist deck is limited by a high-bay door at 4.14m high Nominal configuration is 2-cage (over/under), with bottom (equipment) cage interior height of 4.52m The photo, at left, shows the 4.14m high-bay doors at the top collar of the waste hoist shaft. The perpendicular cross section of the opening is 3.5m x 4.14m, but the bottom cage cross section is 2.87m x 4.5m (and 4.67m into the plane of the photo).

216

Thermal Predictions of the Cooling of Waste Glass Canisters  

SciTech Connect (OSTI)

Radioactive liquid waste from five decades of weapons production is slated for vitrification at the Hanford site. The waste will be mixed with glass forming additives and heated to a high temperature, then poured into canisters within a pour cave where the glass will cool and solidify into a stable waste form for disposal. Computer simulations were performed to predict the heat rejected from the canisters and the temperatures within the glass during cooling. Four different waste glass compositions with different thermophysical properties were evaluated. Canister centerline temperatures and the total amount of heat transfer from the canisters to the surrounding air are reported.

Donna Post Guillen

2014-11-01T23:59:59.000Z

217

Secondary Waste Form Development and OptimizationCast Stone  

SciTech Connect (OSTI)

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

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

2011-07-14T23:59:59.000Z

218

Co-processing of agricultural and biomass waste with coal  

SciTech Connect (OSTI)

A major thrust of our research program is the use of waste materials as co-liquefaction agents for the first-stage conversion of coal to liquid fuels. By fulfilling one or more of the roles of an expensive solvent in the direct coal liquefaction (DCL) process, the waste material is disposed off ex-landfill, and may improve the overall economics of DCL. Work in our group has concentrated on co-liquefaction with waste rubber tires, some results from which are presented elsewhere in these Preprints. In this paper, we report on preliminary results with agricultural and biomass-type waste as co-liquefaction agents.

Stiller, A.H.; Dadyburjor, D.B.; Wann, Ji-Perng [West Virginia Univ., Morgantown, WV (United States)] [and others

1995-12-31T23:59:59.000Z

219

Central Waste Complex (CWC) Waste Analysis Plan  

SciTech Connect (OSTI)

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for waste accepted for storage at the Central Waste Complex (CWC), which is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include the source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

ELLEFSON, M.D.

1999-12-01T23:59:59.000Z

220

Secondary waste form testing : ceramicrete phosphate bonded ceramics.  

SciTech Connect (OSTI)

The cleanup activities of the Hanford tank wastes require stabilization and solidification of the secondary waste streams generated from the processing of the tank wastes. The treatment of these tank wastes to produce glass waste forms will generate secondary wastes, including routine solid wastes and liquid process effluents. Liquid wastes may include process condensates and scrubber/off-gas treatment liquids from the thermal waste treatment. The current baseline for solidification of the secondary wastes is a cement-based waste form. However, alternative secondary waste forms are being considered. In this regard, Ceramicrete technology, developed at Argonne National Laboratory, is being explored as an option to solidify and stabilize the secondary wastes. The Ceramicrete process has been demonstrated on four secondary waste formulations: baseline, cluster 1, cluster 2, and mixed waste streams. Based on the recipes provided by Pacific Northwest National Laboratory, the four waste simulants were prepared in-house. Waste forms were fabricated with three filler materials: Class C fly ash, CaSiO{sub 3}, and Class C fly ash + slag. Optimum waste loadings were as high as 20 wt.% for the fly ash and CaSiO{sub 3}, and 15 wt.% for fly ash + slag filler. Waste forms for physical characterizations were fabricated with no additives, hazardous contaminants, and radionuclide surrogates. Physical property characterizations (density, compressive strength, and 90-day water immersion test) showed that the waste forms were stable and durable. Compressive strengths were >2,500 psi, and the strengths remained high after the 90-day water immersion test. Fly ash and CaSiO{sub 3} filler waste forms appeared to be superior to the waste forms with fly ash + slag as a filler. Waste form weight loss was {approx}5-14 wt.% over the 90-day immersion test. The majority of the weight loss occurred during the initial phase of the immersion test, indicative of washing off of residual unreacted binder components from the waste form surface. Waste forms for ANS 16.1 leach testing contained appropriate amounts of rhenium and iodine as radionuclide surrogates, along with the additives silver-loaded zeolite and tin chloride. The leachability index for Re was found to range from 7.9 to 9.0 for all the samples evaluated. Iodine was below detection limit (5 ppb) for all the leachate samples. Further, leaching of sodium was low, as indicated by the leachability index ranging from 7.6-10.4, indicative of chemical binding of the various chemical species. Target leachability indices for Re, I, and Na were 9, 11, and 6, respectively. Degradation was observed in some of the samples post 90-day ANS 16.1 tests. Toxicity characteristic leaching procedure (TCLP) results showed that all the hazardous contaminants were contained in the waste, and the hazardous metal concentrations were below the Universal Treatment Standard limits. Preliminary scale-up (2-gal waste forms) was conducted to demonstrate the scalability of the Ceramicrete process. Use of minimal amounts of boric acid as a set retarder was used to control the working time for the slurry. Flexibility in treating waste streams with wide ranging compositional make-ups and ease of process scale-up are attractive attributes of Ceramicrete technology.

Singh, D.; Ganga, R.; Gaviria, J.; Yusufoglu, Y. (Nuclear Engineering Division); ( ES)

2011-06-21T23:59:59.000Z

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Radioactive Waste Management (Minnesota)  

Broader source: Energy.gov [DOE]

This section regulates the transportation and disposal of high-level radioactive waste in Minnesota, and establishes a Nuclear Waste Council to monitor the federal high-level radioactive waste...

222

Radioactive Waste Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish policies and guidelines by which the Department of Energy (DOE) manages tis radioactive waste, waste byproducts, and radioactively contaminated surplus facilities.

1984-02-06T23:59:59.000Z

223

Transuranic Waste Requirements  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The guide provides criteria for determining if a waste is to be managed in accordance with DOE M 435.1-1, Chapter III, Transuranic Waste Requirements.

1999-07-09T23:59:59.000Z

224

Waste?to?Energy  

Broader source: Energy.gov [DOE]

Waste?to?Energy Roadmapping Workshop Waste?to?Energy Presentation by Jonathan Male, Director of the Bioenery Technolgies Office, Department of Energy

225

Liquid electrode  

DOE Patents [OSTI]

A dropping electrolyte electrode is described for use in electrochemical analysis of non-polar sample solutions, such as benzene or cyclohexane. The liquid electrode, preferably an aqueous salt solution immiscible in the sample solution, is introduced into the solution in dropwise fashion from a capillary. The electrolyte is introduced at a known rate, thus, the droplets each have the same volume and surface area. The electrode is used in making standard electrochemical measurements in order to determine properties of non-polar sample solutions. 2 figures.

Ekechukwu, A.A.

1994-07-05T23:59:59.000Z

226

Nuclear Waste Disposal: Amounts of Waste  

Science Journals Connector (OSTI)

The term nuclear waste...embraces all residues from the use of radioactive materials, including uses in medicine and industry. The most highly radioactive of these are the spent fuel or reprocessed wastes from co...

2005-01-01T23:59:59.000Z

227

Medical and Biohazardous Waste Generator's Guide (Revision2)  

SciTech Connect (OSTI)

These guidelines describe procedures to comply with all Federal and State laws and regulations and Lawrence Berkeley National Laboratory (LBNL) policy applicable to State-regulated medical and unregulated, but biohazardous, waste (medical/biohazardous waste). These guidelines apply to all LBNL personnel who: (1) generate and/or store medical/biohazardous waste, (2) supervise personnel who generate medical/biohazardous waste, or (3) manage a medical/biohazardous waste pickup location. Personnel generating biohazardous waste at the Joint Genome Institute/Production Genomics Facility (JGI/PGF) are referred to the guidelines contained in Section 9. Section 9 is the only part of these guidelines that apply to JGI/PGF. Medical/biohazardous waste referred to in this Web site includes biohazardous, sharps, pathological and liquid waste. Procedures for proper storage and disposal are summarized in the Solid Medical/Biohazardous Waste Disposal Procedures Chart. Contact the Waste Management Group at 486-7663 if you have any questions regarding medical/biohazardous waste management.

Waste Management Group

2006-11-29T23:59:59.000Z

228

Waste Acceptance Testing of Secondary Waste Forms: Cast Stone, Ceramicrete and DuraLith  

SciTech Connect (OSTI)

To support the selection of a waste form for the liquid secondary wastes from WTP, Washington River Protection Solutions 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 conducting tests on four candidate waste forms to evaluate their ability to meet potential waste acceptance criteria for immobilized secondary wastes that would be placed in the IDF. All three waste forms demonstrated compressive strengths above the minimum 3.45 MPa (500 psi) set as a target for cement-based waste forms. Further, none of the waste forms showed any significant degradation in compressive strength after undergoing thermal cycling (30 cycles in a 10 day period) between -40 C and 60 C or water immersion for 90 days. The three leach test methods are intended to measure the diffusion rates of contaminants from the waste forms. Results are reported in terms of diffusion coefficients and a leachability index (LI) calculated based on the diffusion coefficients. A smaller diffusion coefficient and a larger LI are desired. The NRC, in its Waste Form Technical Position (NRC 1991), provides recommendations and guidance regarding methods to demonstrate waste stability for land disposal of radioactive waste. Included is a recommendation to conduct leach tests using the ANS 16.1 method. The resulting leachability index (LI) should be greater than 6.0. For Hanford secondary wastes, the LI > 6.0 criterion applies to sodium leached from the waste form. For technetium and iodine, higher targets of LI > 9 for Tc and LI > 11 for iodine have been set based on early waste-disposal risk and performance assessment analyses. The results of these three leach tests conducted for a total time between 11days (ASTM C1308) to 90 days (ANS 16.1) showed: (1) Technetium diffusivity: ANSI/ANS 16.1, ASTM C1308, and EPA 1315 tests indicated that all the waste forms had leachability indices better than the target LI > 9 for technetium; (2) Rhenium diffusivity: Cast Stone 2M specimens, when tested using EPA 1315 protocol, had leachability indices better than the target LI > 9 for technetium based on rhenium as a surrogate for technetium. All other waste forms tested by ANSI/ANS 16.1, ASTM C1308, and EPA 1315 test methods had leachability indices that were below the target LI > 9 for Tc based on rhenium release. These studies indicated that use of Re(VII) as a surrogate for 99Tc(VII) in low temperature secondary waste forms containing reductants will provide overestimated diffusivity values for 99Tc. Therefore, it is not appropriate to use Re as a surrogate 99Tc in future low temperature waste form studies. (3) Iodine diffusivity: ANSI/ANS 16.1, ASTM C1308, and EPA 1315 tests indicated that the three waste forms had leachability indices that were below the target LI > 11 for iodine. Therefore, it may be necessary to use a more effective sequestering material than silver zeolite used in two of the waste forms (Ceramicrete and DuraLith); (4) Sodium diffusivity: All the waste form specimens tested by the three leach methods (ANSI/ANS 16.1, ASTM C1308, and EPA 1315) exceeded the target LI value of 6; (5) All three leach methods (ANS 16.1, ASTM C1308 and EPA 1315) provided similar 99Tc diffusivity values for both short-time transient diffusivity effects as well as long-term ({approx}90 days) steady diffusivity from each of the three tested waste forms (Cast Stone 2M, Ceramicrete and DuraLith). Therefore, any one of the three methods can be used to determine the contaminant diffusivities from a selected waste form.

Mattigod, Shas V.; Westsik, Joseph H.; Chung, Chul-Woo; Lindberg, Michael J.; Parker, Kent E.

2011-08-12T23:59:59.000Z

229

Annual report on the development and characterization of solidified forms for nuclear wastes, 1979  

SciTech Connect (OSTI)

Development and characterization of solidified nuclear waste forms is a major continuing effort at Pacific Northwest Laboratory. Contributions from seven programs directed at understanding chemical composition, process conditions, and long-term behaviors of various nuclear waste forms are included in this report. The major findings of the report are included in extended figure captions that can be read as brief technical summaries of the research, with additional information included in a traditional narrative format. Waste form development proceeded on crystalline and glass materials for high-level and transuranic (TRU) wastes. Leaching studies emphasized new areas of research aimed at more basic understanding of waste form/aqueous solution interactions. Phase behavior and thermal effects research included studies on crystal phases in defense and TRU waste glasses and on liquid-liquid phase separation in borosilicate waste glasses. Radiation damage effects in crystals and glasses from alpha decay and from transmutation are reported.

Chick, L.A.; McVay, G.L.; Mellinger, G.B.; Roberts, F.P.

1980-12-01T23:59:59.000Z

230

Treatability study of Tank E-3-1 waste: mixed waste stream SR-W049  

SciTech Connect (OSTI)

Treatability studies were conducted for tank E-3-1 waste which was previously characterized in WSRC-RP-87-0078. The waste was determined to be mixed waste because it displayed the characteristic of metal toxicity for Hg and Cr and was also contaminated with low levels of radionuclides. Two types of treatments for qualifying this waste suitable for land disposal were evaluated: ion exchange and stabilization with hydraulic materials (portland cement, slag and magnesium phosphate cement). These treatments were selected for testing because: (1) Both treatments can be carried out as in-drum processes., (2) Cement stabilization is the RCRA/LDR best developed available technology (BDAT) for Hg (less than 280 mg/L) and for Cr., and (3) Ion exchange via Mag-Sep is a promising alternative technology for in drum treatment of liquid wastes displaying metal toxicity. Cement stabilization of the E-3-1 material ( supernate and settled solids) resulted in waste forms which passed the TCLP test for both Hg and Cr. However, the ion exchange resins tested were ineffective in removing the Hg from this waste stream. Consequently, cement stabilization is recommended for a treatment of the five drums of the actual waste.

Langton, C.A. [Westinghouse Savannah River Company, AIKEN, SC (United States)

1997-08-21T23:59:59.000Z

231

WasteTraining Booklet Waste & Recycling Impacts  

E-Print Network [OSTI]

WasteTraining Booklet #12;Waste & Recycling Impacts Environment: The majority of our municipal jobs while recycling 10,000 tons of waste creates 36 jobs. Environment: Recycling conserves resources. It takes 95% less energy to make aluminum from recycled aluminum than from virgin materials, 60% less

Saldin, Dilano

232

UK Energy Statistics: Renewables and Waste, Commodity Balances (2010) |  

Open Energy Info (EERE)

403 403 Varnish cache server Browse Upload data GDR 429 Throttled (bot load) Error 429 Throttled (bot load) Throttled (bot load) Guru Meditation: XID: 2142288403 Varnish cache server UK Energy Statistics: Renewables and Waste, Commodity Balances (2010) Dataset Summary Description Annual commodity balances (supply, consumption) for renewables and waste in the UK from 1998 to 2009. Published as part of the Digest of UK energy statistics (DUKES), by the UK Department of Energy & Climate Change (DECC). Waste includes: wood waste, farm waste, sewage gas, landfill gas, waste and tyres. Renewables includes: wood, plant-based biomass, geothermal and active solar heat, hydro, wind, wave and tidal, and liquid biofuels. These data were used to produce Tables 7.1 to 7.3 in the Digest of United Kingdom Energy Statistics 2010 (available: http://decc.gov.uk/assets/decc/Statistics/publications/dukes/348-dukes-2...).

233

Savannah River Site Contractor Achieves Tank Waste Milestone | Department  

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

Contractor Achieves Tank Waste Milestone Contractor Achieves Tank Waste Milestone Savannah River Site Contractor Achieves Tank Waste Milestone February 2, 2012 - 12:00pm Addthis Pictured here is a component of the Interim Salt Disposition Process — known as Modular Caustic Side Solvent Extraction Unit (MCU) — that helped Savannah River Remediation process more than 500,000 gallons of salt waste since October last year, a contract milestone. Pictured here is a component of the Interim Salt Disposition Process - known as Modular Caustic Side Solvent Extraction Unit (MCU) - that helped Savannah River Remediation process more than 500,000 gallons of salt waste since October last year, a contract milestone. AIKEN, S.C. - The Savannah River Site's liquid waste contractor recently achieved a contract milestone by processing 500,000 gallons of

234

Recycling of CdTe photovoltaic waste  

DOE Patents [OSTI]

A method for extracting and reclaiming metals from scrap CdTe photovoltaic cells and manufacturing waste by leaching the metals in dilute nitric acid, leaching the waste with a leaching solution comprising nitric acid and water, skimming any plastic material from the top of the leaching solution, separating the glass substrate from the liquid leachate, adding a calcium containing base to the leachate to precipitate Cd and Te, separating the precipitated Cd and Te from the leachate, and recovering the calcium-containing base.

Goozner, Robert E. (Charlotte, NC); Long, Mark O. (Charlotte, NC); Drinkard, Jr., William F. (Charlotte, NC)

1999-04-27T23:59:59.000Z

235

Engineering-Scale Demonstration of DuraLith and Ceramicrete Waste Forms  

SciTech Connect (OSTI)

To support the selection of a waste form for the liquid secondary wastes from the Hanford Waste Immobilization and Treatment Plant, Washington River Protection Solutions (WRPS) has initiated secondary waste form testing on four candidate waste forms. Two of the candidate waste forms have not been developed to scale as the more mature waste forms. This work describes engineering-scale demonstrations conducted on Ceramicrete and DuraLith candidate waste forms. Both candidate waste forms were successfully demonstrated at an engineering scale. A preliminary conceptual design could be prepared for full-scale production of the candidate waste forms. However, both waste forms are still too immature to support a detailed design. Formulations for each candidate waste form need to be developed so that the material has a longer working time after mixing the liquid and solid constituents together. Formulations optimized based on previous lab studies did not have sufficient working time to support large-scale testing. The engineering-scale testing was successfully completed using modified formulations. Further lab development and parametric studies are needed to optimize formulations with adequate working time and assess the effects of changes in raw materials and process parameters on the final product performance. Studies on effects of mixing intensity on the initial set time of the waste forms are also needed.

Josephson, Gary B.; Westsik, Joseph H.; Pires, Richard P.; Bickford, Jody; Foote, Martin W.

2011-09-23T23:59:59.000Z

236

Hanford Site annual dangerous waste report: Volume 2, Generator dangerous waste report, radioactive mixed waste  

SciTech Connect (OSTI)

This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, waste designation, weight, and waste designation.

NONE

1994-12-31T23:59:59.000Z

237

Tank Farms and Waste Feed Delivery - 12507  

SciTech Connect (OSTI)

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. Our discussion of the Tank Farms and Waste Feed Delivery will cover progress made to date with Base and Recovery Act funding in reducing the risk posed by tank waste and in preparing for the initiation of waste treatment at Hanford. 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 underground storage tanks range in capacity from 55,000 gallons to more than 1 million gallons. The tanks were constructed with carbon steel and reinforced concrete. There are eighteen groups of tanks, called 'tank farms', some having as few as two tanks and others up to sixteen tanks. Between 1943 and 1964, 149 single-shell tanks were built at Hanford in the 200 West and East Areas. Heat generated by the waste and the composition of the waste caused an estimated 67 of these single-shell tanks to leak into the ground. Washington River Protection Solutions is the prime contractor responsible for the safe management of this waste. WRPS' mission is to reduce the risk to the environment that is posed by the waste. All of the pumpable liquids have been removed from the single-shell tanks and transferred to the double-shell tanks. What remains in the single-shell tanks are solid and semi-solid wastes. Known as salt-cakes, they have the consistency of wet beach sand. Some of the waste resembles small broken ice, or whitish crystals. Because the original pumps inside the tanks were designed to remove only liquid waste, other methods have been developed to reach the remaining waste. Access to the tank waste is through long, typically skinny pipes, called risers, extending out of the tanks. It is through these pipes that crews are forced to send machines and devices into the tanks that are used to break up the waste or push it toward a pump. These pipes range in size from just a few inches to just over a foot in diameter because they were never intended to be used in this manner. As part of the agreement regulating Hanford cleanup, crews must remove at least 99% of the material in every tank on the site, or at least as much waste that can be removed based on available technology. To date, seven single-shell tanks have been emptied, and work is underway in another 10 tanks in preparation for additional retrieval activities. Two barriers have been installed over single-shell tanks to prevent the intrusion of surface water down to the tanks, with additional barriers planned for the future. Single and double-shell tank integrity analyses are ongoing. Because the volume of the waste generated through plutonium production exceeded the capacity of the single-shell tanks, between 1968 and 1986 Hanford engineers built 28 double-shell tanks. These tanks were studied and made with a second shell to surround the carbon steel and reinforced concrete. The double-shell tanks have not leaked any of their waste. (authors)

Fletcher, Thomas; Charboneau, Stacy; Olds, Erik [US DOE (United States)

2012-07-01T23:59:59.000Z

238

Guidance Document Cryogenic Liquids  

E-Print Network [OSTI]

Guidance Document Cryogenic Liquids [This is a brief and general summary. Read the full MSDS for more details before handling.] Introduction: All cryogenic liquids are gases at normal temperature liquefies them. Cryogenic liquids are kept in the liquid state at very low temperatures. Cryogenic liquids

239

Supplement Analysis for Disposal of Polychlorinated Biphenyl-Commingled Transuranic Waste at the Waste Isolation Pilot Plant (DOE/EIS-0026-SA02) (6/23/04)  

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

Disposal of Disposal of Polychlorinated Biphenyl-Commingled Transuranic Waste at the Waste Isolation Pilot Plant (DOE/EIS-0026-SA02) 1.0 Purpose and Need for Action Transuranic (TRU) waste is waste that contains alpha particle-emitting radionuclides with atomic numbers greater than uranium (92) and half-lives greater than 20 years, in concentrations greater than 100 nanocuries per gram of waste. Some TRU wastes are mixed with polychlorinated biphenyls (PCBs) (referred to as PCB-commingled TRU waste). PCBs exist in DOE's TRU waste as mixtures of synthetic organic chemicals with physical properties ranging from oily liquids to waxy solids. Exposure to PCBs can result in adverse health effects. For example, PCBs in blood or in fatty tissue as a result of inhalation, ingestion, or dermal absorption may cause reproductive effects,

240

Recycling of sodium waste  

Science Journals Connector (OSTI)

Recycling of sodium waste ... Methods for handling and recycling a dangerous and costly chemical. ...

Bettina Hubler-Blank; Michael Witt; Herbert W. Roesky

1993-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Central Waste Complex (CWC) Waste Analysis Plan  

SciTech Connect (OSTI)

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for waste accepted for storage at the Central Waste Complex (CWC), which is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include the source special nuclear and by-product material components of mixed waste, radionuclides are not within the scope of this document. The information on radionuclides is provided only for general knowledge. This document has been revised to meet the interim status waste analysis plan requirements of Washington Administrative Code (WAC) 173 303-300(5). When the final status permit is issued, permit conditions will be incorporated and this document will be revised accordingly.

ELLEFSON, M.D.

2000-01-06T23:59:59.000Z

242

Infectious waste feed system  

DOE Patents [OSTI]

An infectious waste feed system for comminuting infectious waste and feeding the comminuted waste to a combustor automatically without the need for human intervention. The system includes a receptacle for accepting waste materials. Preferably, the receptacle includes a first and second compartment and a means for sealing the first and second compartments from the atmosphere. A shredder is disposed to comminute waste materials accepted in the receptacle to a predetermined size. A trough is disposed to receive the comminuted waste materials from the shredder. A feeding means is disposed within the trough and is movable in a first and second direction for feeding the comminuted waste materials to a combustor.

Coulthard, E. James (York, PA)

1994-01-01T23:59:59.000Z

243

A liquid film motor  

Science Journals Connector (OSTI)

It is well known that electro-hydrodynamical effects in freely suspended liquid films can force liquids to flow. Here, we report a purely electrically driven rotation in water and some other liquid suspended film...

A. Amjadi; R. Shirsavar; N. Hamedani Radja

2009-05-01T23:59:59.000Z

244

Radioactive Waste Management Manual  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

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.

1999-07-09T23:59:59.000Z

245

Cementitious waste option scoping study report  

SciTech Connect (OSTI)

A Settlement Agreement between the Department of Energy (DOE) and the State of Idaho mandates that all high-level radioactive waste (HLW) now stored at the Idaho Chemical Processing Plant (ICPP) on the Idaho National Engineering and Environmental Laboratory (INEEL) will be treated so that it is ready to be moved out of Idaho for disposal by a target date of 2035. This study investigates the nonseparations Cementitious Waste Option (CWO) as a means to achieve this goal. Under this option all liquid sodium-bearing waste (SBW) and existing HLW calcine would be recalcined with sucrose, grouted, canisterized, and interim stored as a mixed-HLW for eventual preparation and shipment off-Site for disposal. The CWO waste would be transported to a Greater Confinement Disposal Facility (GCDF) located in the southwestern desert of the US on the Nevada Test Site (NTS). All transport preparation, shipment, and disposal facility activities are beyond the scope of this study. CWO waste processing, packaging, and interim storage would occur over a 5-year period between 2013 and 2017. Waste transport and disposal would occur during the same time period.

Lee, A.E.; Taylor, D.D.

1998-02-01T23:59:59.000Z

246

The Mixed Waste Management Facility monthly report August 1995  

SciTech Connect (OSTI)

The project is concerned with the design of a mixed waste facility to prepare solid and liquid wastes for processing by electrochemical oxidation, molten salt oxidation, wet oxidation, or UV photolysis. The facility will have a receiving and shipping unit, preparation and processing units, off-gas scrubbing, analytical services, water treatment, and transport and storage facilities. This monthly report give task summaries for 25 tasks which are part of the overall design effort.

Streit, R.D.

1995-09-01T23:59:59.000Z

247

Progress Continues Toward Closure of Two Underground Waste Tanks at Savannah River Site  

Broader source: Energy.gov [DOE]

AIKEN, S.C. The EM program at the Savannah River Site (SRS) is filling two radioactive liquid waste tanks with a cement-like grout in an effort to operationally close them this fall.

248

New and Underutilized Technology: Liquid Desiccant Air Conditioner |  

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

Liquid Desiccant Air Conditioner Liquid Desiccant Air Conditioner New and Underutilized Technology: Liquid Desiccant Air Conditioner October 4, 2013 - 4:40pm Addthis The following information outlines key deployment considerations for liquid desiccant air conditioners (LDACs) within the Federal sector. Benefits Liquid desiccant air conditioners deeply dry air using natural gas, solar energy, waste heat, bio-fuel, or other fossil fuels to drive the system. By providing mostly latent cooling, the LDAC controls indoor humidity without overcooling and reheating. This unit is supplemented by an electric chiller or DX air conditioner that sensibly cools the building's recirculation air. The liquid desiccant is a concentrated salt solution that directly absorbs moisture. Application LDACs are applicable in hospital, office, prison, school, and service

249

Frostbite Theater - Liquid Oxygen vs. Liquid Nitrogen - Liquid Oxygen and  

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

Cells vs. Liquid Nitrogen! Cells vs. Liquid Nitrogen! Previous Video (Cells vs. Liquid Nitrogen!) Frostbite Theater Main Index Next Video (Paramagnetism) Paramagnetism Liquid Oxygen and Fire! What happens when nitrogen and oxygen are exposed to fire? [ Show Transcript ] Announcer: Frostbite Theater presents... Cold Cuts! No baloney! Joanna and Steve: Just science! Joanna: Hi! I'm Joanna! Steve: And I'm Steve! Joanna: And this is a test tube of liquid nitrogen! Steve: And this is a test tube of liquid oxygen! Joanna: Let's see what happens when nitrogen and oxygen are exposed to fire. Steve: Fire?! Joanna: Yeah! Steve: Really?! Joanna: Why not! Steve: Okay! Joanna: As nitrogen boils, it changes into nitrogen gas. Because it's so cold, it's denser than the air in the room. The test tube fills up with

250

2401-W Waste storage building closure plan  

SciTech Connect (OSTI)

This plan describes the performance standards met and closure activities conducted to achieve clean closure of the 2401-W Waste Storage Building (2401-W) (Figure I). In August 1998, after the last waste container was removed from 2401-W, the U.S. Department of Energy, Richland Operations Office (DOE-RL) notified Washington State Department of Ecology (Ecology) in writing that the 2401-W would no longer receive waste and would be closed as a Resource Conservation and Recovery Act (RCRA) of 1976 treatment, storage, and/or disposal (TSD) unit (98-EAP-475). Pursuant to this notification, closure activities were conducted, as described in this plan, in accordance with Washington Administrative Code (WAC) 173-303-610 and completed on February 9, 1999. Ecology witnessed the closure activities. Consistent with clean closure, no postclosure activities will be necessary. Because 2401-W is a portion of the Central Waste Complex (CWC), these closure activities become the basis for removing this building from the CWC TSD unit boundary. The 2401-W is a pre-engineered steel building with a sealed concrete floor and a 15.2-centimeter concrete curb around the perimeter of the floor. This building operated from April 1988 until August 1998 storing non-liquid containerized mixed waste. All waste storage occurred indoors. No potential existed for 2401-W operations to have impacted soil. A review of operating records and interviews with cognizant operations personnel indicated that no waste spills occurred in this building (Appendix A). After all waste containers were removed, a radiation survey of the 2401-W floor for radiological release of the building was performed December 17, 1998, which identified no radiological contamination (Appendix B).

LUKE, S.M.

1999-07-15T23:59:59.000Z

251

Aqueous Waste Treatment Plant at Aldermaston  

SciTech Connect (OSTI)

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)

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)

2006-07-01T23:59:59.000Z

252

Waste-to-Energy: Waste Management and Energy Production Opportunities...  

Office of Environmental Management (EM)

Waste-to-Energy: Waste Management and Energy Production Opportunities Waste-to-Energy: Waste Management and Energy Production Opportunities July 24, 2014 9:00AM to 3:30PM EDT U.S....

253

Summary of radioactive solid waste received in the 200 Areas during calendar year 1992  

SciTech Connect (OSTI)

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Field Office, under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1991. This report does not include solid radioactive wastes in storage or disposed of in other areas or facilities such as the underground tank farms, or backlog wastes. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, (WHC 1988), liquid waste data are not included in this document.

Anderson, J.D.; Hagel, D.L.

1992-05-01T23:59:59.000Z

254

Summary of radioactive solid waste received in the 200 Areas during calendar year 1994  

SciTech Connect (OSTI)

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Field Office, under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive material that has been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1994. This report does not include backlog waste: solid radioactive wastes in storage or disposed of in other areas or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria (WHC 1988), liquid waste data are not included in this document.

Anderson, J.D.; Hagel, D.L.

1995-08-01T23:59:59.000Z

255

Summary of radioactive solid waste received in the 200 Areas during calendar year 1993  

SciTech Connect (OSTI)

Westinghouse Hanford Company manages and operates the Hanford Site 200 Areas radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Areas radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1993. This report does not include backlog waste, solid radioactive waste in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, ``Hanford Site Solid Waste Acceptance Criteria,`` (WHC 1988), liquid waste data are not included in this document.

Anderson, J.D.; Hagel, D.L.

1994-09-01T23:59:59.000Z

256

Bioelectrochemical Integration of Waste Heat Recovery, Waste...  

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

and Waste-to-Chemical Conversion with Industrial Gas and Chemical Manufacturing Processes Air Products and Chemicals, Inc. - Allentown, PA A microbial reverse electrodialysis...

257

Bioelectrochemical Integration of Waste Heat Recovery, Waste...  

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

(ex: organic Rankine cycle) High installed KW capital Low temperature waste heat (<100C) is not practicable Further efficiency loss in electrolytic conversion to...

258

Radioactive Waste Management Manual  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

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. The purpose of the Manual is to catalog those procedural requirements and existing practices that ensure that all DOE elements and contractors continue to manage DOE's radioactive waste in a manner that is protective of worker and public health and safety, and the environment. Does not cancel other directives.

1999-07-09T23:59:59.000Z

259

Grid composite for backfill barriers and waste applications  

SciTech Connect (OSTI)

A grid composite for protecting men and longwall mining equipment during longwall shield recovery includes a regular polymer geogrid structure formed by biaxially drawing a continuous sheet of select polypropylene material which is heat bonded to a polyester fabric. The grid composite is secured over caving shields of longwall mining equipment during a longwall mining operation. The polymer grid composite is ideal for waste containment structures, backfill barriers, and silt barriers in construction and mining applications. In waste containment and backfill barriers, the grid composite is used to form a containment structure. It principle function is to contain waste material usually consisting of a liquid with some percentage of solids. 10 figs.

Travis, B.

1994-01-11T23:59:59.000Z

260

Safetygram #9- Liquid Hydrogen  

Broader source: Energy.gov [DOE]

Hydrogen is colorless as a liquid. Its vapors are colorless, odorless, tasteless, and highly flammable.

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

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

SciTech Connect (OSTI)

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.

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

1997-01-07T23:59:59.000Z

262

Liquid effluents 1994 fiscal year work plan: WBS 1.2.2.1  

SciTech Connect (OSTI)

The program mission is to manage current and future liquid effluent streams in a safe, responsible, cost effective and legally compliant manner. This is achieved through planning and integration, public and stakeholder interaction, definition of requirements for generators and provision of timely treatment, storage, disposal capability, and waste minimization of waste streams where applicable.

Ashworth, F.L. Jr.

1993-08-01T23:59:59.000Z

263

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect (OSTI)

This report provides a quantitative inventory and composition (chemical and radioactivity) of calcined waste stored at the Idaho Nuclear Technology and Engineering Center. From December 1963 through May 2000, liquid radioactive wastes generated by spent nuclear fuel reprocessing were converted into a solid, granular form called calcine. This report also contains a description of the calcine storage bins.

M. D. Staiger

2007-06-01T23:59:59.000Z

264

Waste treatment facility passes federal inspection, completes final  

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

23, 2012 23, 2012 Media Contact: Danielle Miller, 208-526-5709 Erik Simpson, 208-390-9464 Waste treatment facility passes federal inspection, completes final milestone, begins startup The Idaho site today initiated the controlled, phased startup of a new waste treatment facility scheduled to begin treating 900,000 gallons of radioactive liquid waste stored in underground tanks at a former Cold War spent nuclear fuel reprocessing facility next month. An exterior view of the Integrated Waste Treatment Unit A U.S. Department of Energy (DOE) operational readiness review team (made up of Subject Matter Experts across the country) in early April identified a dozen issues for the cleanup contractor CH2M-WG Idaho, LLC (CWI) to resolve before the 53,000-square-foot Integrated Waste Treatment Unit

265

Salt Waste Contractor Reaches Contract Milestone | Department of Energy  

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

Salt Waste Contractor Reaches Contract Milestone Salt Waste Contractor Reaches Contract Milestone Salt Waste Contractor Reaches Contract Milestone April 29, 2013 - 12:00pm Addthis Robert Brown, SRR tank farm operator, performs daily inspections of a salt disposition process facility. The inspections and improvement upgrades have resulted in continued successful operations. Robert Brown, SRR tank farm operator, performs daily inspections of a salt disposition process facility. The inspections and improvement upgrades have resulted in continued successful operations. AIKEN, S.C. - The liquid waste cleanup contractor for the EM program at the Savannah River Site (SRS) recently surpassed a 2013 contract milestone by processing more than 600,000 gallons of salt waste. Savannah River Remediation (SRR) salt disposition process facilities

266

Waste Treatment Facility Passes Federal Inspection, Completes Final  

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

Waste Treatment Facility Passes Federal Inspection, Completes Final Waste Treatment Facility Passes Federal Inspection, Completes Final Milestone, Begins Startup Waste Treatment Facility Passes Federal Inspection, Completes Final Milestone, Begins Startup April 23, 2012 - 12:00pm Addthis Media Contact Erik Simpson, 208-390-9464 Danielle Miller, 208-526-5709 The Idaho site today initiated the controlled, phased startup of a new waste treatment facility scheduled to begin treating 900,000 gallons of radioactive liquid waste stored in underground tanks at a former Cold War spent nuclear fuel reprocessing facility next month. A U.S. Department of Energy (DOE) operational readiness review team (made up of Subject Matter Experts across the country) in early April identified a dozen issues for the cleanup contractor CH2M-WG Idaho, LLC (CWI) to

267

Waste Heat Recovery from Industrial Process Heating Equipment -  

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

Waste Heat Recovery from Industrial Process Heating Equipment - Waste Heat Recovery from Industrial Process Heating Equipment - Cross-cutting Research and Development Priorities Speaker(s): Sachin Nimbalkar Date: January 17, 2013 - 11:00am Location: 90-2063 Seminar Host/Point of Contact: Aimee McKane Waste heat is generated from several industrial systems used in manufacturing. The waste heat sources are distributed throughout a plant. The largest source for most industries is exhaust / flue gases or heated air from heating systems. This includes the high temperature gases from burners in process heating, lower temperature gases from heat treat, dryers, and heaters, heat from heat exchangers, cooling liquids and gases etc. The previous studies and direct contact with the industry as well as equipment suppliers have shown that a large amount of waste heat is not

268

Los Alamos low-level waste performance assessment status  

SciTech Connect (OSTI)

This report reviews the documented Los Alamos studies done to assess the containment of buried hazardous wastes. Five sections logically present the environmental studies, operational source terms, transport pathways, environmental dosimetry, and computer model development and use. This review gives a general picture of the Los Alamos solid waste disposal and liquid effluent sites and is intended for technical readers with waste management and environmental science backgrounds but without a detailed familiarization with Los Alamos. The review begins with a wide perspective on environmental studies at Los Alamos. Hydrology, geology, and meteorology are described for the site and region. The ongoing Laboratory-wide environmental surveillance and waste management environmental studies are presented. The next section describes the waste disposal sites and summarizes the current source terms for these sites. Hazardous chemical wastes and liquid effluents are also addressed by describing the sites and canyons that are impacted. The review then focuses on the transport pathways addressed mainly in reports by Healy and Formerly Utilized Sites Remedial Action Program. Once the source terms and potential transport pathways are described, the dose assessment methods are addressed. Three major studies, the waste alternatives, Hansen and Rogers, and the Pantex Environmental Impact Statement, contributed to the current Los Alamos dose assessment methodology. Finally, the current Los Alamos groundwater, surface water, and environmental assessment models for these mesa top and canyon sites are described.

Wenzel, W.J.; Purtymun, W.D.; Dewart, J.M.; Rodgers, J.E. (comps.)

1986-06-01T23:59:59.000Z

269

Characterization of the MVST waste tanks located at ORNL  

SciTech Connect (OSTI)

During the fall of 1996 there was a major effort to sample and analyze the Active Liquid Low-Level Waste (LLLW) tanks at ORNL which include the Melton Valley Storage Tanks (MVST) and the Bethel Valley Evaporator Service Tanks (BVEST). The characterization data summarized in this report was needed to address waste processing options, address concerns of the performance assessment (PA) data for the Waste Isolation Pilot Plant (WIPP), evaluate the characteristics with respect to the waste acceptance criteria (WAC) for WIPP and Nevada Test Site (NTS), address criticality concerns, and meet DOT requirements for transporting the waste. This report only discusses the analytical characterization data for the MVST waste tanks. The isotopic data presented in this report support the position that fissile isotopes of uranium and plutonium were ``denatured`` as required by administrative controls. In general, MVST sludge was found to be both hazardous by RCRA characteristics and the transuranic alpha activity was well about the limit for TRU waste. The characteristics of the MVST sludge relative to the WIPP WAC limits for fissile gram equivalent, plutonium equivalent activity, and thermal power from decay heat, were estimated from the data in this report and found to be far below the upper boundary for any of the remote-handled transuranic waste requirements for disposal of the waste in WIPP.

Keller, J.M.; Giaquinto, J.M.; Meeks, A.M.

1996-12-01T23:59:59.000Z

270

Westinghouse Cementation Facility of Solid Waste Treatment System - 13503  

SciTech Connect (OSTI)

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)

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

2013-07-01T23:59:59.000Z

271

Hanford Dangerous Waste Permit  

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

from tank waste. * Decreases the volume of water to create room in double-shell tanks, allowing them to accept waste from noncompliant single- shell tanks. * Treats up to 1...

272

Hanford Dangerous Waste Permit  

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

trucks for scale. The DSTs have limited capacity and are aging. Maintaining these tanks is important to ensure that waste is ready to supply the Waste Treatment Plant. The...

273

Hazardous Waste Management (Oklahoma)  

Broader source: Energy.gov [DOE]

This article states regulations for the disposal of hazardous waste. It also provides information about permit requirements for the transport, treatment and storage of such waste. It also mentions...

274

Nuclear waste solids  

Science Journals Connector (OSTI)

Glass and polycrystalline materials for high-level radioactive waste immobilization are discussed. Borosilicate glass has been selected as the waste form for defence high-level radwaste in the US. Since releas...

L. L. Hench; D. E. Clark; A. B. Harker

1986-05-01T23:59:59.000Z

275

ABSORBING WIPP BRINES: A TRU WASTE DISPOSAL STRATEGY  

SciTech Connect (OSTI)

Los Alamos National Laboratory (LANL) has completed experiments involving 15 each, 250- liter experimental test containers of transuranic (TRU) heterogeneous waste immersed in two types of brine similar to those found in the underground portion of the Waste Isolation Pilot Plant (WIPP). To dispose of the waste without removing the brine from the test containers, LANL added commercially available cross-linked polyacrylate granules to absorb the 190 liters of brine in each container, making the waste compliant for shipping to the WIPP in a Standard Waste Box (SWB). Prior to performing the absorption, LANL and the manufacturer of the absorbent conducted laboratory and field tests to determine the ratio of absorbent to brine that would fully absorb the liquid. Bench scale tests indicated a ratio of 10 parts Castile brine to one part absorbent and 6.25 parts Brine A to one part absorbent. The minimum ratio of absorbent to brine was sought because headspace in the containers was limited. However, full scale testing revealed that the ratio should be adjusted to be about 15% richer in absorbent. Additional testing showed that the absorbent would not apply more than 13.8 kPa pressure on the walls of the vessel and that the absorbent would still function normally at that pressure and would not degrade in the approximately 5e-4 Sv/hr radioactive field produced by the waste. Heat generation from the absorption was minimal. The in situ absorption created a single waste stream of 8 SWBs whereas the least complicated alternate method of disposal would have yielded at least an additional 2600 liters of mixed low level liquid waste plus about two cubic meters of mixed low level solid waste, and would have resulted in higher risk of radiation exposure to workers. The in situ absorption saved $311k in a combination of waste treatment, disposal, material and personnel costs compared to the least expensive alternative and $984k compared to the original plan.

Yeamans, D. R.; Wrights, R. S.

2002-02-25T23:59:59.000Z

276

Absorbing WIPP brines : a TRU waste disposal strategy.  

SciTech Connect (OSTI)

Los Alamos National Laboratory (LANL) has completed experiments involving 15 each, 250-liter experimental test containers of transuranic (TRU) heterogeneous waste immersed in two types of brine similar to those found in the underground portion of the Waste Isolation Pilot Plant (WIPP). To dispose of the waste without removing the brine from the test containers, LANL added commercially available cross-linked polyacrylate granules to absorb the 190 liters of brine in each container, making the waste compliant for shipping to the WlPP in a Standard Waste Box (SWB). Prior to performing the absorption, LANL and the manufacturer of the absorbent conducted laboratory and field tests to determine the ratio of absorbent to brine that would fully absorb the liquid. Bench scale tests indicated a ratio of 10 parts Castile brine to one part absorbent and 6.25 parts Brine A to one part absorbent. The minimum ratio of absorbent to brine was sought because headspace in the containers was limited. However, full scale testing revealed that the ratio should be adjusted to be about 15% richer in absorbent. Additional testing showed that the absorbent would not apply more than 13.8 kPa pressure on the walls of the vessel and that the absorbent would still function normally at that pressure and would not degrade in the approximately 5e-4 Sv/hr radioactive field produced by the waste. Heat generation from the absorption was minimal. The in situ absorption created a single waste stream of 8 SWBs whereas the least complicated alternate method of disposal would have yielded at least an additional 2600 liters of mixed low level liquid waste plus about two cubic meters of mixed low level solid waste, and would have resulted in higher risk of radiation exposure to workers. The in situ absorption saved $3 1 lk in a combination of waste treatment, disposal, material and personnel costs compared to the least expensive alternative and $984k compared to the original plan.

Yeamans, D. R. (David R.); Wright, R. (Robert)

2002-01-01T23:59:59.000Z

277

Short Communication Bioreduction and precipitation of uranium in ionic liquid aqueous  

E-Print Network [OSTI]

with uranium from mining and milling operations, radioactive wastes, and from nuclear accidents is a majorShort Communication Bioreduction and precipitation of uranium in ionic liquid aqueous solution t s Uranium forms various complexes with ionic liquids. Uranium bioreduction was affected by the type

Ohta, Shigemi

278

Waste disposal package  

DOE Patents [OSTI]

This is a claim for a waste disposal package including an inner or primary canister for containing hazardous and/or radioactive wastes. The primary canister is encapsulated by an outer or secondary barrier formed of a porous ceramic material to control ingress of water to the canister and the release rate of wastes upon breach on the canister. 4 figs.

Smith, M.J.

1985-06-19T23:59:59.000Z

279

Operational test report for 2706-T complex liquid transfer system  

SciTech Connect (OSTI)

This document is the Operational Test Report (OTR). It enters the Record Copy of the W-259 Operational Test Procedure (HNF-3610) into the document retrieval system. Additionally, the OTR summarizes significant issues associated with testing the 2706-T waste liquid transfer and storage system.

BENZEL, H.R.

1999-09-01T23:59:59.000Z

280

Conditioning Matrices of Liquid Scintillation Cocktails Contaminated with Tritium  

SciTech Connect (OSTI)

This paper describes a viable solidification technology to convert the liquid scintillation cocktail into a stable form which minimizes the probability to release tritium in the environment.This radioactive waste type is generated by the radio-chemical analysis lab of a CANDU nuclear power plant.

Dianu, Magdalena [Institute for Nuclear Research (Romania)

2005-07-15T23:59:59.000Z

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Developments in Very Low Level Waste/Exempt Waste Assay at AWE - 12000  

SciTech Connect (OSTI)

Portable High Resolution Gamma Spectrometry (HRGS) has been developed, for Very Low Level Waste (VLLW) and Exempt Waste (EW) assay at AWE, in order to meet the latest reduced clearance levels of < 1 Bq/g (or Bq/cm{sup 2}) for uranium (U) contaminated wastes and < 0.15 Bq/g (or Bq/cm{sup 2}) for plutonium (Pu) wastes. Studies have focused on a 10 kg bag of low density soft waste monitored either as a rotating cylinder, contained within a shortened plastic drum liner, or as a contained disk monitored on each broad side. Liquid and surface contaminated metal wastes have also been studied. It was established that monitoring the disk gave the best detection levels, but uncertainties rose more sharply, compared to the cylinder, as detector offset was reduced. Exempt detection levels were readily achieved for all U compositions encountered at AWE and for most Pu compositions (via Am-241 measurement). However, performance will need to be enhanced for those Pu compositions with relatively high Pu/Am-241 activity ratios. Recommendations are made for further developments to enhance the performance of this technique so that exempt clearance can be achieved for all Pu compositions encountered. (author)

Miller, T.J. [AWE, Aldermaston, Reading, Berkshire, RG7 4PR (United Kingdom)

2012-07-01T23:59:59.000Z

282

Identifying Mixed Chemical and Radioactive Waste Mixed waste is: any waste material containing both radioactive materials  

E-Print Network [OSTI]

Identifying Mixed Chemical and Radioactive Waste Mixed waste is: any waste material containing both as noted on the list, you do not have a mixed waste and it may be managed as a normal radioactive waste radioactive waste after initially dating the container, the hold for decay time is extended, but you cannot

Straight, Aaron

283

Radioactive Waste Management Manual  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

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. Admin Chg 2, dated 6-8-11, cancels DOE M 435.1-1 Chg 1.

1999-07-09T23:59:59.000Z

284

Liquid level detector  

DOE Patents [OSTI]

A liquid level detector for low pressure boilers. A boiler tank, from which apor, such as steam, normally exits via a main vent, is provided with a vertical side tube connected to the tank at the desired low liquid level. When the liquid level falls to the level of the side tube vapor escapes therethrough causing heating of a temperature sensitive device located in the side tube, which, for example, may activate a liquid supply means for adding liquid to the boiler tank. High liquid level in the boiler tank blocks entry of vapor into the side tube, allowing the temperature sensitive device to cool, for example, to ambient temperature.

Grasso, Albert P. (Vernon, CT)

1986-01-01T23:59:59.000Z

285

Liquid level detector  

DOE Patents [OSTI]

A liquid level detector for low pressure boilers. A boiler tank, from which vapor, such as steam, normally exits via a main vent, is provided with a vertical side tube connected to the tank at the desired low liquid level. When the liquid level falls to the level of the side tube vapor escapes therethrough causing heating of a temperature sensitive device located in the side tube, which, for example, may activate a liquid supply means for adding liquid to the boiler tank. High liquid level in the boiler tank blocks entry of vapor into the side tube, allowing the temperature sensitive device to cool, for example, to ambient temperature.

Grasso, A.P.

1984-02-21T23:59:59.000Z

286

Transuranic Waste Transportation Working Group Agenda | Department...  

Office of Environmental Management (EM)

Transuranic Waste Transportation Working Group Agenda Transuranic Waste Transportation Working Group Agenda Transuranic Waste Transportation Working Group Agenda More Documents &...

287

Waste Isolation Pilot Plant Transportation Security | Department...  

Office of Environmental Management (EM)

Waste Isolation Pilot Plant Transportation Security Waste Isolation Pilot Plant Transportation Security Waste Isolation Pilot Plant Transportation Security More Documents &...

288

WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT  

SciTech Connect (OSTI)

The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status.

J. D. Bigbee

2000-06-21T23:59:59.000Z

289

Process development for remote-handled mixed-waste treatment  

SciTech Connect (OSTI)

The Oak Ridge National Laboratory (ORNL) is developing a treatment process for remote-handled (RH) liquid transuranic mixed waste governed by the concept of minimizing the volume of waste requiring disposal. This task is to be accomplished by decontaminating the bulk components so the process effluent can be disposed with less risk and expense. Practical processes have been demonstrated on the laboratory scale for removing cesium 137 and strontium 90 isotopes from the waste, generating a concentrated waste volume, and rendering the bulk of the waste nearly radiation free for downstream processing. The process is projected to give decontamination factors of 10{sup 4} for cesium and 10{sup 3} for strontium. Because of the extent of decontamination, downstream processing will be contact handled. The transuranic, radioactive fraction of the mixed waste stream will be solidified using a thin-film evaporator and/or microwave solidification system. Resultant solidified waste will be disposed at the Waste Isolation Pilot Plant (WIPP). 8 refs., 2 figs., 3 tabs.

Berry, J.B.; Campbell, D.O.; Lee, D.D.; White, T.L.

1990-01-01T23:59:59.000Z

290

Tank Waste Corporate Board Meeting 03/05/09 | Department of Energy  

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

Tank Waste Corporate Board Meeting 03/05/09 Tank Waste Corporate Board Meeting 03/05/09 Tank Waste Corporate Board Meeting 03/05/09 The following documents are associated with the Tank Waste Corporate Board Meeting held on March 5th, 2009. Overview of Integrated Waste Treatment Unit Desired PU Loading During Vitrification HLW System Integrated Project Team Waste Determination and Section 3116 of the 2005 National Defense Authorization Act - HQ Perspective Status of Art & Practice of Performance Assessment within the DOE Complex Experience from the Short Course on Introduction to Nuclear Chemistry and Fuel Cycle Separations and Future Educational Opportunities Role of Liquid Waste Pretreatment Technologies in Solving the DOE Clean-up Mission Performance Assessment Community of Practice Action Item Review and Status

291

Report: Findings, Conclusions, and Recommendations Concerning the Waste Treatment and Immobilization Project at Hanford  

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

EMAB Tank Waste Subcommittee Summary Report 1 EMAB Tank Waste Subcommittee Summary Report 1 Report of Findings, Conclusions, and Recommendations Concerning the Waste Treatment and Immobilization Project (WTP) at Hanford Submitted by the Environmental Management Advisory Board Tank Waste Subcommittee September 15, 2010 Introduction In May 2010, the Department of Energy established the Environmental Management Tank Waste Subcommittee (EM-TWS). The EM-TWS was charged with conducting an independent technical review of liquid waste capital and operations projects related to the Office of Environmental Management (EM) tank waste cleanup programs at Hanford, Washington; the Savannah River Site in South Carolina; the Idaho National Laboratory; and the West Valley Demonstration Project in New York. The EM-TWS's review focused on the facilities being

292

Viscosity, specific (for liquids)  

Science Journals Connector (OSTI)

n. The ratio between the viscosity of a liquid and the viscosity of water at the same temperature. Specific viscosity is sometimes used interchangeably with relative viscosity for liquids.

2007-01-01T23:59:59.000Z

293

Tank Waste and Waste Processing | Department of Energy  

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

Tank Waste and Waste Processing Tank Waste and Waste Processing Tank Waste and Waste Processing Tank Waste and Waste Processing The Defense Waste Processing Facility set a record by producing 267 canisters filled with glassified waste in a year. New bubbler technology and other enhancements will increase canister production in the future. The Defense Waste Processing Facility set a record by producing 267 canisters filled with glassified waste in a year. New bubbler technology and other enhancements will increase canister production in the future. A Savannah River Remediation employee uses a manipulator located inside a shielded enclosure at the Defense Waste Processing Facility where the melter is pouring molten glass inside a canister. A Savannah River Remediation employee uses a manipulator located inside a

294

Liquid Piston Stirling Engines  

Science Journals Connector (OSTI)

The Fluidyne liquid piston engine is a simple free-piston Stirling engine that can be made from nothing more...

Graham Walker Ph. D.; J. R. Senft Ph.D.

1985-01-01T23:59:59.000Z

295

Bioelectrochemical Integration of Waste Heat Recovery, Waste...  

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

electrolytic cell, designed to integrate waste heat recovery (i.e a microbial heat recovery cell or MHRC), can operate as a fuel cell and convert effluent streams into...

296

New Waste Calcining Facility (NWCF) Waste Streams  

SciTech Connect (OSTI)

This report addresses the issues of conducting debris treatment in the New Waste Calcine Facility (NWCF) decontamination area and the methods currently being used to decontaminate material at the NWCF.

K. E. Archibald

1999-08-01T23:59:59.000Z

297

Solid Waste Management Plan. Revision 4  

SciTech Connect (OSTI)

The waste types discussed in this Solid Waste Management Plan are Municipal Solid Waste, Hazardous Waste, Low-Level Mixed Waste, Low-Level Radioactive Waste, and Transuranic Waste. The plan describes for each type of solid waste, the existing waste management facilities, the issues, and the assumptions used to develop the current management plan.

NONE

1995-04-26T23:59:59.000Z

298

Waste Confidence Discussion | Department of Energy  

Office of Environmental Management (EM)

Waste Confidence Discussion Waste Confidence Discussion Long-Term Waste Confidence Update. Waste Confidence Discussion More Documents & Publications Status Update: Extended Storage...

299

EM Waste and Materials Disposition & Transportation | Department...  

Office of Environmental Management (EM)

EM Waste and Materials Disposition & Transportation EM Waste and Materials Disposition & Transportation DOE's Radioactive Waste Management Priorities: Continue to manage waste...

300

Transuranic (TRU) Waste | Department of Energy  

Office of Environmental Management (EM)

Transuranic (TRU) Waste Transuranic (TRU) Waste Transuranic (TRU) Waste Defined by the WIPP Land Withdrawal Act as "waste containing more than 100 nanocuries of alpha-emitting...

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Results of Soil Vapor Extraction of a Chlorinated Solvent Dnapl Waste Site at the Rocky Flats Superfund Site  

Science Journals Connector (OSTI)

A full scale Soil Vapor Extraction (SVE) system was evaluated for remediation of subsurface contamination of the chlorinated Dense Non-Aqueous Phase Liquids (DNAPL) at a waste site at the Rocky Flats Environmenta...

S. Grace; E. Dille

1995-01-01T23:59:59.000Z

302

Ferrocyanide tank waste stability  

SciTech Connect (OSTI)

Ferrocyanide wastes were generated at the Hanford Site during the mid to late 1950s as a result of efforts to create more tank space for the storage of high-level nuclear waste. The ferrocyanide process was developed to remove [sup 137]CS from existing waste and newly generated waste that resulted from the recovery of valuable uranium in Hanford Site waste tanks. During the course of research associated with the ferrocyanide process, it was recognized that ferrocyanide materials, when mixed with sodium nitrate and/or sodium nitrite, were capable of violent exothermic reaction. This chemical reactivity became an issue in the 1980s, when safety issues associated with the storage of ferrocyanide wastes in Hanford Site tanks became prominent. These safety issues heightened in the late 1980s and led to the current scrutiny of the safety issues associated with these wastes, as well as current research and waste management programs. Testing to provide information on the nature of possible tank reactions is ongoing. This document supplements the information presented in Summary of Single-Shell Tank Waste Stability, WHC-EP-0347, March 1991 (Borsheim and Kirch 1991), which evaluated several issues. This supplement only considers information particular to ferrocyanide wastes.

Fowler, K.D.

1993-01-01T23:59:59.000Z

303

6 - Nuclear Waste Regulations  

Science Journals Connector (OSTI)

The most influential national and international bodies providing recommendations on radiation protection are described, including the International Commission on Radiological Protection (ICRP) and the International Atomic Energy Agency (IAEA). Protection philosophies and the ICRP general principles of radiation protection are discussed. Radioactive material regulations and sources of radiation are explained. Criteria of exemption from regulatory control are discussed with examples of exemption levels for naturally occurring and radioactive waste radionuclides. Clearance of both moderate and bulk amounts of materials from regulatory control is also explained, including examples of EU and the UK regulations. Dose limits recommended by the ICRP are given, as well as the main principles of control of radiation hazards. Nuclear waste classification schemes are outlined, including the IAEA classification scheme. A brief explanation of nuclear waste classes including exempt waste, very short-lived waste, very low-level waste, low-level waste, intermediate-level waste and high-level waste is given. Examples of waste classification schemes are given, including that of the UK.

M.I. Ojovan; W.E. Lee

2014-01-01T23:59:59.000Z

304

Hanford Tank Waste Information Enclosure 1 Hanford Tank Waste Information  

E-Print Network [OSTI]

Hanford Tank Waste Information Enclosure 1 1 Hanford Tank Waste Information 1.0 Summary This information demonstrates the wastes in the twelve Hanford Site tanks meet the definition of transuranic (TRU. The wastes in these twelve (12) tanks are not high-level waste (HLW), and contain more than 100 nanocuries

305

Energy from Waste UK Joint Statement on Energy from Waste  

E-Print Network [OSTI]

Energy from Waste UK Joint Statement on Energy from Waste Read more overleaf Introduction Energy from waste provides us with an opportunity for a waste solution and a local source of energy rolled,itcan onlyaddressaportionofthewastestream andisnotsufficientonitsown. Energy obtained from the combustion of residual waste (Energy from

306

Stabilization of compactible waste  

SciTech Connect (OSTI)

This report summarizes the results of series of experiments performed to determine the feasibility of stabilizing compacted or compactible waste with polymers. The need for this work arose from problems encountered at disposal sites attributed to the instability of this waste in disposal. These studies are part of an experimental program conducted at Brookhaven National Laboratory (BNL) investigating methods for the improved solidification/stabilization of DOE low-level wastes. The approach taken in this study was to perform a series of survey type experiments using various polymerization systems to find the most economical and practical method for further in-depth studies. Compactible dry bulk waste was stabilized with two different monomer systems: styrene-trimethylolpropane trimethacrylate (TMPTMA) and polyester-styrene, in laboratory-scale experiments. Stabilization was accomplished by wetting or soaking compactible waste (before or after compaction) with monomers, which were subsequently polymerized. Three stabilization methods are described. One involves the in-situ treatment of compacted waste with monomers in which a vacuum technique is used to introduce the binder into the waste. The second method involves the alternate placement and compaction of waste and binder into a disposal container. In the third method, the waste is treated before compaction by wetting the waste with the binder using a spraying technique. A series of samples stabilized at various binder-to-waste ratios were evaluated through water immersion and compression testing. Full-scale studies were conducted by stabilizing two 55-gallon drums of real compacted waste. The results of this preliminary study indicate that the integrity of compacted waste forms can be readily improved to ensure their long-term durability in disposal environments. 9 refs., 10 figs., 2 tabs.

Franz, E.M.; Heiser, J.H. III; Colombo, P.

1990-09-01T23:59:59.000Z

307

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

SciTech Connect (OSTI)

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

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

1980-09-01T23:59:59.000Z

308

HIGH TEMPERATURE TREATMENT OF INTERMEDIATE-LEVEL RADIOACTIVE WASTES - SIA RADON EXPERIENCE  

SciTech Connect (OSTI)

This review describes high temperature methods of low- and intermediate-level radioactive waste (LILW) treatment currently used at SIA Radon. Solid and liquid organic and mixed organic and inorganic wastes are subjected to plasma heating in a shaft furnace with formation of stable leach resistant slag suitable for disposal in near-surface repositories. Liquid inorganic radioactive waste is vitrified in a cold crucible based plant with borosilicate glass productivity up to 75 kg/h. Radioactive silts from settlers are heat-treated at 500-700 0C in electric furnace forming cake following by cake crushing, charging into 200 L barrels and soaking with cement grout. Various thermochemical technologies for decontamination of metallic, asphalt, and concrete surfaces, treatment of organic wastes (spent ion-exchange resins, polymers, medical and biological wastes), batch vitrification of incinerator ashes, calcines, spent inorganic sorbents, contaminated soil, treatment of carbon containing 14C nuclide, reactor graphite, lubricants have been developed and implemented.

Sobolev, I.A.; Dmitriev, S.A.; Lifanov, F.A.; Kobelev, A.P.; Popkov, V.N.; Polkanov, M.A.; Savkin, A.E.; Varlakov, A.P.; Karlin, S.V.; Stefanovsky, S.V.; Karlina, O.K.; Semenov, K.N.

2003-02-27T23:59:59.000Z

309

SRS Waste Tanks 5 and 6 Are Operationally Closed | Department of Energy  

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

SRS Waste Tanks 5 and 6 Are Operationally Closed SRS Waste Tanks 5 and 6 Are Operationally Closed SRS Waste Tanks 5 and 6 Are Operationally Closed December 19, 2013 - 12:00pm Addthis The final amount of grout is poured into Tank 6, marking the operational closure of Tanks 5 and 6. The final amount of grout is poured into Tank 6, marking the operational closure of Tanks 5 and 6. Media Contacts Amy Caver, Amy.Caver@srs.gov, 803-952-7213 Rick Kelley, Rick.Kelley@srs.gov, 803-208-0198 AIKEN, S.C. - Savannah River Remediation (SRR), the liquid waste contractor at the U.S. Department of Energy (DOE) Savannah River Site, has removed from service two more Cold War-era liquid radioactive waste tanks, marking the third and fourth tanks operationally closed by SRR in the last 14 months. Grouting and closure of Tanks 5 and 6 were completed approximately two

310

Final Environmental Impact Statement for Treating Transuranic (TRU)/Alpha Low-level Waste at the Oak Ridge National Laboratory Oak Ridge, Tennessee  

SciTech Connect (OSTI)

The DOE proposes to construct, operate, and decontaminate/decommission a TRU Waste Treatment Facility in Oak Ridge, Tennessee. The four waste types that would be treated at the proposed facility would be remote-handled TRU mixed waste sludge, liquid low-level waste associated with the sludge, contact-handled TRU/alpha low-level waste solids, and remote-handled TRU/alpha low-level waste solids. The mixed waste sludge and some of the solid waste contain metals regulated under the Resource Conservation and Recovery Act and may be classified as mixed waste. This document analyzes the potential environmental impacts associated with five alternatives--No Action, the Low-Temperature Drying Alternative (Preferred Alternative), the Vitrification Alternative, the Cementation Alternative, and the Treatment and Waste Storage at Oak Ridge National Laboratory (ORNL) Alternative.

N /A

2000-06-30T23:59:59.000Z

311

Proceedings of the US Department of Energy Office of Environmental Restoration and Waste Management  

SciTech Connect (OSTI)

The fifth of a series of waste minimization (WMIN)/reduction workshops (Waste Reduction Workshop V) was held at the Little Tree Inn in Idaho Falls, Idaho, on July 24--26, 1990. The workshops are held under the auspices of the US Department of Energy's (DOE's) Office of Environmental Restoration and Waste Management (EM). The purpose of this workshop was to provide a forum for sharing site activities in WMIN/reduction planning. Topics covered were management commitment, organizational structure, goal setting, reporting requirements, data bases and tracking systems, pollution prevention, awareness and incentives, information exchange, process waste assessment (PWA) implementation, and recycling internal and external. The workshops assist DOE waste-generating sites in implementing WMIN/reduction programs, plans, and activities, thus providing for optimal waste reduction within the DOE complex. All wastes are considered within this discipline: liquid, solid, and airborne, within the categories of high-level waste (HLW), transuranic waste (TRU), low-level waste (LLW), hazardous waste, and mixed waste.

Not Available

1990-09-01T23:59:59.000Z

312

REMOVAL OF CESIUM FROM SAVANNAH RIVER SITE WASTE WITH SPHERICAL RESORCINOL FORMALDEHYDE ION EXCHANGE RESIN EXPERIMENTAL TESTS  

SciTech Connect (OSTI)

A principal goal at the Savannah River Site (SRS) is to safely dispose of the large volume of liquid nuclear waste held in many storage tanks. In-tank ion exchange (IX) columns are being considered for cesium removal. The spherical form of resorcinol formaldehyde ion exchange resin (sRF) is being evaluated for decontamination of dissolved saltcake waste at SRS, which is generally lower in potassium and organic components than Hanford waste. The sRF performance with SRS waste was evaluated in two phases: resin batch contacts and IX column testing with both simulated and actual dissolved salt waste. The tests, equipment, and results are discussed.

Duignan, M.; Nash, C.

2010-03-31T23:59:59.000Z

313

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

SciTech Connect (OSTI)

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.

Nash, C.; Duignan, M.

2010-01-14T23:59:59.000Z

314

Pioneering Nuclear Waste Disposal  

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

18 18 19 T he WIPP's first waste receipt, 11 years later than originally planned, was a monumental step forward in the safe management of nuclear waste. Far from ending, however, the WIPP story has really just begun. For the next 35 years, the DOE will face many challenges as it manages a complex shipment schedule from transuranic waste sites across the United States and continues to ensure that the repository complies with all regulatory requirements. The DOE will work to maintain the highest level of safety in waste handling and trans- portation. Coordination with sites Disposal operations require coordination with sites that will ship transuranic waste to the WIPP and include periodic certification of waste characterization and handling practices at those facilities. During the WIPP's

315

High level nuclear waste  

SciTech Connect (OSTI)

The DOE Division of Waste Products through a lead office at Savannah River is developing a program to immobilize all US high-level nuclear waste for terminal disposal. DOE high-level wastes include those at the Hanford Plant, the Idaho Chemical Processing Plant, and the Savannah River Plant. Commercial high-level wastes, for which DOE is also developing immobilization technology, include those at the Nuclear Fuel Services Plant and any future commercial fuels reprocessing plants. The first immobilization plant is to be the Defense Waste Processing Facility at Savannah River, scheduled for 1983 project submission to Congress and 1989 operation. Waste forms are still being selected for this plant. Borosilicate glass is currently the reference form, but alternate candidates include concretes, calcines, other glasses, ceramics, and matrix forms.

Crandall, J L

1980-01-01T23:59:59.000Z

316

Underground waste barrier structure  

DOE Patents [OSTI]

Disclosed is an underground waste barrier structure that consists of waste material, a first container formed of activated carbonaceous material enclosing the waste material, a second container formed of zeolite enclosing the first container, and clay covering the second container. The underground waste barrier structure is constructed by forming a recessed area within the earth, lining the recessed area with a layer of clay, lining the clay with a layer of zeolite, lining the zeolite with a layer of activated carbonaceous material, placing the waste material within the lined recessed area, forming a ceiling over the waste material of a layer of activated carbonaceous material, a layer of zeolite, and a layer of clay, the layers in the ceiling cojoining with the respective layers forming the walls of the structure, and finally, covering the ceiling with earth.

Saha, Anuj J. (Hamburg, NY); Grant, David C. (Gibsonia, PA)

1988-01-01T23:59:59.000Z

317

Synthesizing Optimal Waste Blends  

Science Journals Connector (OSTI)

Vitrification of tank wastes to form glass is a technique that will be used for the disposal of high-level waste at Hanford. ... Durability restrictions ensure that the resultant glass meets the quantitative criteria for disposal/long-term storage in a repository. ... If glasses are formulated to minimize the volume of glass that would be produced, then the cost of processing the waste and storing the resultant glass would be greatly reduced. ...

Venkatesh Narayan; Urmila M. Diwekar; Mark Hoza

1996-10-08T23:59:59.000Z

318

Liquid Wall Chambers  

SciTech Connect (OSTI)

The key feature of liquid wall chambers is the use of a renewable liquid layer to protect chamber structures from target emissions. Two primary options have been proposed and studied: wetted wall chambers and thick liquid wall (TLW) chambers. With wetted wall designs, a thin layer of liquid shields the structural first wall from short ranged target emissions (x-rays, ions and debris) but not neutrons. Various schemes have been proposed to establish and renew the liquid layer between shots including flow-guiding porous fabrics (e.g., Osiris, HIBALL), porous rigid structures (Prometheus) and thin film flows (KOYO). The thin liquid layer can be the tritium breeding material (e.g., flibe, PbLi, or Li) or another liquid metal such as Pb. TLWs use liquid jets injected by stationary or oscillating nozzles to form a neutronically thick layer (typically with an effective thickness of {approx}50 cm) of liquid between the target and first structural wall. In addition to absorbing short ranged emissions, the thick liquid layer degrades the neutron flux and energy reaching the first wall, typically by {approx}10 x x, so that steel walls can survive for the life of the plant ({approx}30-60 yrs). The thick liquid serves as the primary coolant and tritium breeding material (most recent designs use flibe, but the earliest concepts used Li). In essence, the TLW places the fusion blanket inside the first wall instead of behind the first wall.

Meier, W R

2011-02-24T23:59:59.000Z

319

State Waste Discharge Permit application: 200-E Powerhouse Ash Pit  

SciTech Connect (OSTI)

As part of the Hanford Federal Facility Agreement and Consent Order negotiations, the US Department and Energy, Richland Operations Office, the US Environmental Protection Agency, and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground on the Hanford Site which affect groundwater or have the potential to affect groundwater would be subject to permitting under the structure of Chapter 173-216 (or 173-218 where applicable) of the Washington Administrative Code, the State Waste Discharge Permit Program. This document constitutes the State Waste Discharge Permit application for the 200-E Powerhouse Ash Pit. The 200-E Powerhouse Ash Waste Water discharges to the 200-E Powerhouse Ash Pit via dedicated pipelines. The 200-E Ash Waste Water is the only discharge to the 200-E Powerhouse Ash Pit. The 200-E Powerhouse is a steam generation facility consisting of a coal-handling and preparation section and boilers.

Atencio, B.P.

1994-06-01T23:59:59.000Z

320

State Waste Discharge Permit application: 200-W Powerhouse Ash Pit  

SciTech Connect (OSTI)

As part of the Hanford Federal Facility Agreement and Consent Order negotiations; the US Department of Energy, Richland Operations Office, the US Environmental Protection Agency, and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground on the Hanford Site which affect groundwater or have the potential to affect groundwater would be subject to permitting under the structure of Chapter 173-216 (or 173-218 where applicable) of the Washington Administrative Code, the State Waste Discharge Permit Program. This document constitutes the State Waste Discharge Permit application for the 200-W Powerhouse Ash Pit. The 200-W Powerhouse Ash Waste Water discharges to the 200-W Powerhouse Ash Pit via dedicated pipelines. The 200-W Powerhouse Ash Waste Water is the only discharge to the 200-W Powerhouse Ash Pit. The 200-W Powerhouse is a steam generation facility consisting of a coal-handling and preparation section and boilers.

Atencio, B.P.

1994-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Sliding Luttinger liquid phases  

Science Journals Connector (OSTI)

We study systems of coupled spin-gapped and gapless Luttinger liquids. First, we establish the existence of a sliding Luttinger liquid phase for a system of weakly coupled parallel quantum wires, with and without disorder. It is shown that the coupling can stabilize a Luttinger liquid phase in the presence of disorder. We then extend our analysis to a system of crossed Luttinger liquids and establish the stability of a non-Fermi-liquid state: the crossed sliding Luttinger liquid phase. In this phase the system exhibits a finite-temperature, long-wavelength, isotropic electric conductivity that diverges as a power law in temperature T as T?0. This two-dimensional system has many properties of a true isotropic Luttinger liquid, though at zero temperature it becomes anisotropic. An extension of this model to a three-dimensional stack exhibits a much higher in-plane conductivity than the conductivity in a perpendicular direction.

Ranjan Mukhopadhyay; C. L. Kane; T. C. Lubensky

2001-07-09T23:59:59.000Z

322

Waste Confidence Discussion  

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

Long-Term Long-Term Waste Confidence Update Christine Pineda Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission National Transportation Stakeholders Forum May 2012 ♦ Knoxville, Tennessee Long-Term Update Draft Report, "Background and Preliminary Assumptions for an Environmental Impact Statement- Long-Term Waste Confidence Update" Elements of the Long-Term Update - Draft environmental impact statement - Draft Waste Confidence Decision - Proposed Waste Confidence Rule based on the EIS and Decision, if applicable 2 Overview of Draft Report Background and assumptions report is first step in process. Basic topics in the report are:

323

Norcal Waste Systems, Inc.  

SciTech Connect (OSTI)

Fact sheet describes the LNG long-haul heavy-duty trucks at Norcal Waste Systems Inc.'s Sanitary Fill Company.

Not Available

2002-12-01T23:59:59.000Z

324

Section 24: Waste Characterization  

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

Energy (DOE). 1995b. Transuranic Waste Baseline Inventory Report (Revision 2, December). DOECAO-95-1121. ERMS 531643. Carlsbad Area Office, Carlsbad, NM. PDF Author U.S....

325

Hanford Dangerous Waste Permit  

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

training, security) * Closure plan Tank-Related Permit Units New * 149 single-shell tanks (SSTs) * 28 double-shell tanks (DSTs) Existing * 242-A Evaporator * Waste Treatment...

326

Waste Heat Recovery  

Office of Environmental Management (EM)

DRAFT - PRE-DECISIONAL - DRAFT 1 Waste Heat Recovery 1 Technology Assessment 2 Contents 3 1. Introduction to the TechnologySystem ......

327

Electronic Waste Transformation  

Science Journals Connector (OSTI)

Electronic Waste Transformation ... Instead, entrepreneurial individuals and small businesses recover valuable metals such as copper from obsolete equipment through activities such as burning. ...

CHERYL HOGUE

2012-04-01T23:59:59.000Z

328

Waste minimization assessment procedure  

SciTech Connect (OSTI)

Perry Nuclear Power Plant began developing a waste minimization plan early in 1991. In March of 1991 the plan was documented following a similar format to that described in the EPA Waste Minimization Opportunity Assessment Manual. Initial implementation involved obtaining management's commitment to support a waste minimization effort. The primary assessment goal was to identify all hazardous waste streams and to evaluate those streams for minimization opportunities. As implementation of the plan proceeded, non-hazardous waste streams routinely generated in large volumes were also evaluated for minimization opportunities. The next step included collection of process and facility data which would be useful in helping the facility accomplish its assessment goals. This paper describes the resources that were used and which were most valuable in identifying both the hazardous and non-hazardous waste streams that existed on site. For each material identified as a waste stream, additional information regarding the materials use, manufacturer, EPA hazardous waste number and DOT hazard class was also gathered. Once waste streams were evaluated for potential source reduction, recycling, re-use, re-sale, or burning for heat recovery, with disposal as the last viable alternative.

Kellythorne, L.L. (Centerior Energy, Cleveland, OH (United States))

1993-01-01T23:59:59.000Z

329

Vitrification of waste  

DOE Patents [OSTI]

A method is described for encapsulating and immobilizing waste for disposal. Waste, preferably, biologically, chemically and radioactively hazardous, and especially electronic wastes, such as circuit boards, are placed in a crucible and heated by microwaves to a temperature in the range of approximately 300 C to 800 C to incinerate organic materials, then heated further to a temperature in the range of approximately 1100 C to 1400 C at which temperature glass formers present in the waste will cause it to vitrify. Glass formers, such as borosilicate glass, quartz or fiberglass can be added at the start of the process to increase the silicate concentration sufficiently for vitrification.

Wicks, G.G.

1999-04-06T23:59:59.000Z

330

Avoidable waste management costs  

SciTech Connect (OSTI)

This report describes the activity based costing method used to acquire variable (volume dependent or avoidable) waste management cost data for routine operations at Department of Energy (DOE) facilities. Waste volumes from environmental restoration, facility stabilization activities, and legacy waste were specifically excluded from this effort. A core team consisting of Idaho National Engineering Laboratory, Los Alamos National Laboratory, Rocky Flats Environmental Technology Site, and Oak Ridge Reservation developed and piloted the methodology, which can be used to determine avoidable waste management costs. The method developed to gather information was based on activity based costing, which is a common industrial engineering technique. Sites submitted separate flow diagrams that showed the progression of work from activity to activity for each waste type or treatability group. Each activity on a flow diagram was described in a narrative, which detailed the scope of the activity. Labor and material costs based on a unit quantity of waste being processed were then summed to generate a total cost for that flow diagram. Cross-complex values were calculated by determining a weighted average for each waste type or treatability group based on the volume generated. This study will provide DOE and contractors with a better understanding of waste management processes and their associated costs. Other potential benefits include providing cost data for sites to perform consistent cost/benefit analysis of waste minimization and pollution prevention (WMIN/PP) options identified during pollution prevention opportunity assessments and providing a means for prioritizing and allocating limited resources for WMIN/PP.

Hsu, K.; Burns, M.; Priebe, S.; Robinson, P.

1995-01-01T23:59:59.000Z

331

Waste Isolation Pilot Plant  

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

September 19, 2014 - No second release at WIPP September 12, 2014 - Waste hoist transformer replacement September 09, 2014 - Additional areas cleared in WIPP underground...

332

Vitrification of waste  

DOE Patents [OSTI]

A method for encapsulating and immobilizing waste for disposal. Waste, preferably, biologically, chemically and radioactively hazardous, and especially electronic wastes, such as circuit boards, are placed in a crucible and heated by microwaves to a temperature in the range of approximately 300.degree. C. to 800.degree. C. to incinerate organic materials, then heated further to a temperature in the range of approximately 1100.degree. C. to 1400.degree. C. at which temperature glass formers present in the waste will cause it to vitrify. Glass formers, such as borosilicate glass, quartz or fiberglass can be added at the start of the process to increase the silicate concentration sufficiently for vitrification.

Wicks, George G. (Aiken, SC)

1999-01-01T23:59:59.000Z

333

Second Generation Waste Package Design Study  

SciTech Connect (OSTI)

The following describes the objectives of Project Activity 023 Second Generation Waste Package Design Study under DOE Cooperative Agreement DE-FC28-04RW12232. The objectives of this activity are: to review the current YMP baseline environment and establish corrosion testenvironments representative of the range of dry to intermittently wet conditions expected in the drifts as a function of time; to demonstrate the oxidation and corrosion resistance of A588 weathering steel and reference Alloy 22 samples in the representative dry to intermittently dry conditions; and to evaluate backfill and design features to improve the thermal performance analyses of the proposed second-generation waste packages using existing models developed at the University of Nevada, Reno(UNR). The work plan for this project activity consists of three major tasks: Task 1. Definition of expected worst-case environments (humidity, liquid composition and temperature) at waste package outer surfaces as a function of time, and comparison with environments defined in the YMP baseline; Task 2. Oxidation and corrosion tests of proposed second-generation outer container material; and Task 3. Second Generation waste package thermal analyses. Full funding was not provided for this project activity.

Armijo, J.S.; Misra, M.; Kar, Piyush

2007-06-28T23:59:59.000Z

334

Waste Loading Enhancements for Hanford Low-Activity Waste Glasses  

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

WASTE LOADING ENHANCEMENTS FOR HANFORD LOW-ACTIVITY WASTE GLASSES Albert A. Kruger, Glass Scientist DOE-WTP Project Office Engineering Division US Department of Energy Richland,...

335

Tank Waste Committee Page 1  

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

of a PA is to examine the final waste disposition at Hanford, such as waste in the tanks at C-Farm. Vince said the quest is to model waste movement over 10,000 years,...

336

Packaging and transportation of radioactive liquid at the U.S. Department of Energy Hanford Site  

SciTech Connect (OSTI)

Beginning in the 1940`s, radioactive liquid waste has been generated at the US Department of Energy (DOE) Hanford Site as a result of defense material production. The liquid waste is currently stored in 177 underground storage tanks. As part of the tank remediation efforts, Type B quantity packagings for the transport of large volumes of radioactive liquids are required. There are very few Type B liquid packagings in existence because of the rarity of large-volume radioactive liquid payloads in the commercial nuclear industry. Development of aboveground transport systems for large volumes of radioactive liquids involves institutional, economic, and technical issues. Although liquid shipments have taken place under DOE-approved controlled conditions within the boundaries of the Hanford Site for many years, offsite shipment requires compliance with DOE, US Nuclear Regulatory Commission (NRC), and US Department of Transportation (DOT) directives and regulations. At the present time, no domestic DOE nor NRC-certified Type B packagings with the appropriate level of shielding are available for DOT-compliant transport of radioactive liquids in bulk volumes. This paper will provide technical details regarding current methods used to transport such liquids on and off the Hanford Site, and will provide a status of packaging development programs for future liquid shipments.

Smith, R.J.

1995-02-01T23:59:59.000Z

337

Processing results of 1,800 gallons of mercury and radioactively contaminated mixed waste rinse solution  

SciTech Connect (OSTI)

The mercury-contaminated rinse solution (INEL waste ID{number_sign} 123; File 8 waste) was successfully treated at the Idaho National Engineering Laboratory (INEL). This waste was generated during the decontamination of the Heat Transfer Reactor Experiment 3 (HTRE-3) reactor shield tank. Approximately 1,800 gal of waste was generated and was placed into 33 drums. Each drum contained precipitated sludge material ranging from 1--10 in. in depth, with the average depth of about 2.5 in. The pH of each drum varied from 3--11. The bulk liquid waste had a mercury level of 7.0 mg/l, which exceeded the Resource Conservation and Recovery Act (RCRA) limit of 0.2 mg/l. The average liquid bulk radioactivity was about 2.1 pCi/ml, while the average sludge contamination was about 13,800 pci/g. Treatment of the waste required separation of the liquid from the sludge, filtration, pH adjustment, and ion exchange. Because of difficulties in processing, three trials were required to reduce the mercury levels to below the RCRA limit. In the first trial, insufficient filtration of the waste allowed solid particulate produced during pH adjustment to enter into the ion exchange columns and ultimately the waste storage tank. In the second trial, the waste was filtered down to 0.1 {mu} to remove all solid mercury compounds. However, before filtration could take place, a solid mercury complex dissolved and mercury levels exceeded the RCRA limit after filtration. In the third trial, the waste was filtered through 0.3-A filters and then passed through the S-920 resin to remove the dissolved mercury. The resulting solution had mercury levels at 0.0186 mg/l and radioactivity of 0.282 pCi/ml. This solution was disposed of at the TAN warm waste pond, TAN782, TSF-10.

Thiesen, B.P.

1993-01-01T23:59:59.000Z

338

State Waste Discharge Permit application, 100-N Sewage Lagoon  

SciTech Connect (OSTI)

As part of the Hanford Federal Facility Agreement and Consent Order negotiations (Ecology et al. 1994), the US Department of Energy, Richland Operations Office, the US Environmental Protection Agency, and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground on the Hanford Site which affect groundwater or have the potential to affect groundwater would be subject to permitting under the structure of Chapter 173--216 (or 173--218 where applicable) of the Washington Administrative Code, the State Waste Discharge Permit Program. As a result of this decision, the Washington State Department of Ecology and the US Department of Energy, Richland Operations Office entered into Consent Order No. DE 91NM-177, (Ecology and DOE-RL 1991). This document constitutes the State Waste Discharge Permit application for the 100-N Sewage Lagoon. Since the influent to the sewer lagoon is domestic waste water, the State Waste Discharge Permit application for Public Owned Treatment Works Discharges to Land was used. Although the 100-N Sewage Lagoon is not a Public Owned Treatment Works, the Public Owned Treatment Works application is more applicable than the application for industrial waste water. The 100-N Sewage Lagoon serves the 100-N Area and other Hanford Site areas by receiving domestic waste from two sources. A network of sanitary sewer piping and lift stations transfers domestic waste water from the 100-N Area buildings directly to the 100-N Sewage Lagoon. Waste is also received by trucks that transport domestic waste pumped from on site septic tanks and holding tanks. Three ponds comprise the 100-N Sewage Lagoon treatment system. These include a lined aeration pond and stabilization pond, as well as an unlined infiltration pond. Both piped-in and trucked-in domestic waste is discharged directly into the aeration pond.

Not Available

1994-06-01T23:59:59.000Z

339

In situ vitrification: application analysis for stabilization of transuranic waste  

SciTech Connect (OSTI)

The in situ vitrification process builds upon the electric melter technology previously developed for high-level waste immobilization. In situ vitrification converts buried wastes and contaminated soil to an extremely durable glass and crystalline waste form by melting the materials, in place, using joule heating. Once the waste materials have been solidified, the high integrity waste form should not cause future ground subsidence. Environmental transport of the waste due to water or wind erosion, and plant or animal intrusion, is minimized. Environmental studies are currently being conducted to determine whether additional stabilization is required for certain in-ground transuranic waste sites. An applications analysis has been performed to identify several in situ vitrification process limitations which may exist at transuranic waste sites. Based on the process limit analysis, in situ vitrification is well suited for solidification of most in-ground transuranic wastes. The process is best suited for liquid disposal sites. A site-specific performance analysis, based on safety, health, environmental, and economic assessments, will be required to determine for which sites in situ vitrification is an acceptable disposal technique. Process economics of in situ vitrification compare favorably with other in-situ solidification processes and are an order of magnitude less than the costs for exhumation and disposal in a repository. Leachability of the vitrified product compares closely with that of Pyrex glass and is significantly better than granite, marble, or bottle glass. Total release to the environment from a vitrified waste site is estimated to be less than 10/sup -5/ parts per year. 32 figures, 30 tables.

Oma, K.H.; Farnsworth, R.K.; Rusin, J.M.

1982-09-01T23:59:59.000Z

340

Hanford land disposal restrictions plan for mixed wastes  

SciTech Connect (OSTI)

Since the early 1940s, the Hanford Site has been involved in the production and purification of nuclear defense materials. These production activities have resulted in the generation of large quantities of liquid and solid radioactive mixed waste. This waste is subject to regulation under authority of both the Resource Conservation and Recovery Act of 1976 (RCRA) and the Atomic Energy Act. The State of Washington Department of Ecology (Ecology), the US Environmental Protection Agency (EPA), and the US Department of Energy (DOE) have entered into an agreement, the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) to bring Hanford Site Operations into compliance with dangerous waste regulations. The Tri-Party Agreement was amended to require development of the Hanford Land Disposal Restrictions Plan for Mixed Wastes (this plan) to comply with land disposal restrictions requirements for radioactive mixed waste. The Tri-Party Agreement requires, and the this plan provides, the following sections: Waste Characterization Plan, Storage Report, Treatment Report, Treatment Plan, Waste Minimization Plan, a schedule, depicting the events necessary to achieve full compliance with land disposal restriction requirements, and a process for establishing interim milestones. 34 refs., 28 figs., 35 tabs.

Not Available

1990-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Hanford high-level waste evaporator/crystallizer corrosion evaluation  

SciTech Connect (OSTI)

The US Department of Energy, Hanford Site nuclear reservation, located in Southeastern Washington State, is currently home to 61 Mgal of radioactive waste stored in 177 large underground storage tanks. As an intermediate waste volume reduction, the 242-A Evaporator/Crystallizer processes waste solutions from most of the operating laboratories and plants on the Hanford Site. The waste solutions are concentrated in the Evaporator/Crystallizer to a slurry of liquid and crystallized salts. This concentrated slurry is returned to Hanford Site waste tanks at a significantly reduced volume. The Washington State Department of Ecology Dangerous Waste Regulations, WAC 173-393 require that a tank system integrity assessment be completed and maintained on file at the facility for all dangerous waste tank systems. This corrosion evaluation was performed in support of the 242-A Evaporator/Crystallizer Tank System Integrity Assessment Report. This corrosion evaluation provided a comprehensive compatibility study of the component materials and corrosive environments. Materials used for the Evaporator components and piping include austenitic stainless steels (SS) (primarily ASTM A240, Type 304L) and low alloy carbon steels (CS) (primarily ASTM A53 and A106) with polymeric or asbestos gaskets at flanged connections. Building structure and secondary containment is made from ACI 301-72 Structural Concrete for Buildings and coated with a chemically resistant acrylic coating system.

Ohl, P.C.; Carlos, W.C.

1993-10-01T23:59:59.000Z

342

The technological Aspects of Liquid Radioactive Waste Treatment  

SciTech Connect (OSTI)

The Final Treatment Center (FTC) at Mochovce Nuclear Power Plant (NPP) have been tested with radioactive media during commissioning phase (02 - 04/2007) and then introduced to trial operation in 10/2007. One-year trial operation of facility is planned. This paper introducing the short description of FTC technological equipments and the description of technological procedures including the basic technological parameters of both used technologies. The paper is dealing with the description and commentary of inactive/model testing phase and the radioactive test phase, too. A commentary to trial operation preparation works is given. The evaluation of experience gained in the phases of Center commissioning and partially trial operation as well is a part of this paper. The identification of key interdependencies within process parameters and treatment product properties is carried out. The fulfillment of the projected output parameters for all technological facilities and the achievement of required qualitative parameters of individual treated RAW products are displayed. (authors)

Krajc, T.; Stubna, M.; Zatkulak, M. [VUJE, a.s., Trnava (Slovakia); Slezak, M.; Remias, V. [JAVYS, a.s., Bohunice (Slovakia)

2008-07-01T23:59:59.000Z

343

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

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

A process vessel ventilation system is being installed in a facility that houses two tanks that will process decontaminated salt solution at the Saltstone Production Facility. A...

344

Voluntary Protection Program Onsite, Liquid Waste Contract Savannah...  

Energy Savers [EERE]

2011 More Documents & Publications Voluntary Protection Program Onsite Review, Savannah River Site - May 2010 VPP Program Document Voluntary Protection Program Onsite Review, Los...

345

Chapter 19 - Nuclear Waste Fund  

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

Nuclear Waste Fund 19-1 Nuclear Waste Fund 19-1 CHAPTER 19 NUCLEAR WASTE FUND 1. INTRODUCTION. a. Purpose. This chapter establishes the financial, accounting, and budget policies and procedures for civilian and defense nuclear waste activities, as authorized in Public Law 97-425, the Nuclear Waste Policy Act, as amended, referred to hereafter as the Act. b. Applicability. This chapter applies to all Departmental elements, including the National Nuclear Security Administration, and activities that are funded by the Nuclear Waste Fund (NWF) or the Defense Nuclear Waste Disposal appropriation. c. Background. The Act established the Office of Civilian Radioactive Waste Management (OCRWM) and assigned it responsibility for the management

346

Solid Waste Rules (New Hampshire)  

Broader source: Energy.gov [DOE]

The solid waste statute applies to construction and demolition debris, appliances, recyclables, and the facilities that collect, process, and dispose of solid waste. DES oversees the management of...

347

Solid Waste Management (North Carolina)  

Broader source: Energy.gov [DOE]

The Solid Waste Program regulates safe management of solid waste through guidance, technical assistance, regulations, permitting, environmental monitoring, compliance evaluation and enforcement....

348

Waste Management | Department of Energy  

Energy Savers [EERE]

Management Waste Management Oak Ridge has an onsite CERCLA disposal facility, the Environmental Management Waste Management Facility, that reduces cleanup and transportation costs....

349

Municipal Waste Combustion (New Mexico)  

Broader source: Energy.gov [DOE]

This rule establishes requirements for emissions from, and design and operation of, municipal waste combustion units. "Municipal waste"means all materials and substances discarded from residential...

350

Waste Disposal | Department of Energy  

Office of Environmental Management (EM)

Disposal Waste Disposal Trucks transport debris from Oak Ridges cleanup sites to the onsite CERCLA disposal area, the Environmental Management Waste Management Facility....

351

22 - Radioactive waste disposal  

Science Journals Connector (OSTI)

Publisher Summary This chapter discusses the disposal of radioactive wastes that arise from a great variety of sources, including the nuclear fuel cycle, beneficial uses of isotopes, and radiation by institutions. Spent fuel contains uranium, plutonium, and highly radioactive fission products. The spent fuel is accumulating, awaiting the development of a high-level waste repository. It is anticipated that a multi-barrier system involving packaging and geologic media will provide protection of the public over the centuries. The favored method of disposal is in a mined cavity deep underground. In some countries, reprocessing the fuel assemblies permits recycling of materials and disposal of smaller volumes of solidified waste. Transportation of wastes is done by casks and containers designed to withstand severe accidents. Low-level wastes come from research and medical procedures and from a variety of activation and fission sources at a reactor site. They generally can be given near-surface burial. Isotopes of special interest are cobalt-60 and cesium-137. Transuranic wastes are being disposed of in the Waste Isolation Pilot Plant. Decommissioning of reactors in the future will contribute a great deal of low-level radioactive waste.

Raymond L. Murray

2001-01-01T23:59:59.000Z

352

Nuclear waste solutions  

DOE Patents [OSTI]

High efficiency removal of technetium values from a nuclear waste stream is achieved by addition to the waste stream of a precipitant contributing tetraphenylphosphonium cation, such that a substantial portion of the technetium values are precipitated as an insoluble pertechnetate salt.

Walker, Darrel D. (1684 Partridge Dr., Aiken, SC 29801); Ebra, Martha A. (129 Hasty Rd., Aiken, SC 29801)

1987-01-01T23:59:59.000Z

353

Radioactive waste storage issues  

SciTech Connect (OSTI)

In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state`s boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected.

Kunz, D.E.

1994-08-15T23:59:59.000Z

354

68 Glass Technology Vol. 45 No. 2 April 2004 Proc. VII Symp. on Crystallisation in Glasses and Liquids, Sheffield, 69 July 2003 Proc. VII Symp. on Crystallisation in Glasses and Liquids, Sheffield, 69 July 2003 Glass Technol., 2004, 45, 6870  

E-Print Network [OSTI]

68 Glass Technology Vol. 45 No. 2 April 2004 Proc. VII Symp. on Crystallisation in Glasses and Liquids, Sheffield, 6­9 July 2003 Proc. VII Symp. on Crystallisation in Glasses and Liquids, Sheffield, 6­9 July 2003 Glass Technol., 2004, 45, 68­70 The behaviour of a simulant Magnox waste glass

Sheffield, University of

355

Heavy Liquid Metal Reactor Development - Nuclear Engineering Division  

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

> Heavy Liquid Metal Reactor Development > Heavy Liquid Metal Reactor Development Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Nuclear Data Program Advanced Reactor Development Overview Advanced Fast Reactor (AFR) Heavy Liquid Metal Reactor Development Generation IV Nuclear Waste Form and Repository Performance Modeling Nuclear Energy Systems Design and Development Other Capabilities Work with Argonne Contact us For Employees Site Map Help Advanced Reactor Development and Technology Heavy Liquid Metal Reactor Development Bookmark and Share STAR-LM: Simplified, Modular, Small Reactor Featuring Flow-thru Fuel Cartridge STAR-LM: Simplified, Modular, Small Reactor Featuring Flow-thru Fuel Cartridge. Click on image to view larger image. Argonne has traditionally been the foremost institute in the US for

356

Selection and use of equipment for the sampling of liquids  

SciTech Connect (OSTI)

The selection of sampling equipment for the collection of liquid waste is based on factors such as the viscosity of the sample matrix, matrix compatibility with the construction materials of the sampling device, and the physical location of the sampling point. This report provides information relating to sampling from such matrices as ground and surface waters, vadose zones, containerized liquids, lagoons, and seeps. It is intended to be a reference tool for personnel involved with the collection of liquid samples throughout the Department of Energy complex. This report provides a general overview of many liquid sampling devices used and for each device it provides a short narrative regarding applicability, an outline of the basic procedure for use, a list of advantages and disadvantages, and an illustration.

Johnson, M.

1995-11-01T23:59:59.000Z

357

Liquid level detector  

DOE Patents [OSTI]

A liquid level detector for conductive liquids for vertical installation in a tank, the detector having a probe positioned within a sheath and insulated therefrom by a seal so that the tip of the probe extends proximate to but not below the lower end of the sheath, the lower end terminating in a rim that is provided with notches, said lower end being tapered, the taper and notches preventing debris collection and bubble formation, said lower end when contacting liquid as it rises will form an airtight cavity defined by the liquid, the interior sheath wall, and the seal, the compression of air in the cavity preventing liquid from further entry into the sheath and contact with the seal. As a result, the liquid cannot deposit a film to form an electrical bridge across the seal.

Tshishiku, Eugene M. (Augusta, GA)

2011-08-09T23:59:59.000Z

358

Pioneering Nuclear Waste Disposal  

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

T h e W a s t e I s o l a t i o n P i l o t P l a n t DOE 1980. Final Environmental Impact Statement, Waste Isolation Pilot Plant. DOE/EIS-0026, Washington, DC, Office of Environmental Management, U.S. Department of Energy. DOE 1981. Waste Isolation Pilot Plant (WIPP): Record of Decision. Federal Register, Vol. 46, No. 18, p. 9162, (46 Federal Register 9162), January 28, 1981. U.S. Department of Energy. DOE 1990. Final Supplement Environmental Impact Statement, Waste Isolation Pilot Plant. DOE/EIS-0026-FS, Washington, DC, Office of Environmental Management, U.S. Department of Energy. DOE 1990. Record of Decision: Waste Isolation Pilot Plant. Federal Register, Vol. 55, No. 121, 25689-25692, U.S. Department of Energy. DOE 1994. Comparative Study of Waste Isolation Pilot Plant (WIPP) Transportation Alternatives.

359

HLW Glass Waste Loadings  

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

HLW HLW Glass Waste Loadings Ian L. Pegg Vitreous State Laboratory The Catholic University of America Washington, DC Overview Overview  Vitrification - general background  Joule heated ceramic melter (JHCM) technology  Factors affecting waste loadings  Waste loading requirements and projections  WTP DWPF  DWPF  Yucca Mountain License Application requirements on waste loading  Summary Vitrification  Immobilization of waste by conversion into a glass  Internationally accepted treatment for HLW  Why glass?  Amorphous material - able to incorporate a wide spectrum of elements over wide ranges of composition; resistant to radiation damage  Long-term durability - natural analogs Relatively simple process - amenable to nuclearization at large  Relatively simple process - amenable to nuclearization at large scale  There

360

Microsoft Word - M3LW-12IN0602062 Report  

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

The framework of the FW-PHM software consists of four main components: Diagnostic Advisor; Asset Fault Signature (AFS) Database; RUL Advisor; and RUL Signature Database. Idaho...

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Microsoft Word - M3LW-12IN0602062 Report  

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

181 181 Online Monitoring Technical Basis and Analysis Framework for Large Power Transformers; Interim Report for FY 2012 Nancy J. Lybeck, Vivek Agarwal, Binh T. Pham, Heather D. Medema, Kirk Fitzgerald September 2012 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trade mark, manufacturer, or otherwise,

362

Safety analysis of exothermic reaction hazards associated with the organic liquid layer in tank 241-C-103  

SciTech Connect (OSTI)

Safety hazards associated with the interim storage of a potentially flammable organic liquid in waste Tank C-103 are identified and evaluated. The technical basis for closing the unreviewed safety question (USQ) associated with the floating liquid organic layer in this tank is presented.

Postma, A.K.; Bechtold, D.B.; Borsheim, G.L.; Grisby, J.M.; Guthrie, R.L.; Kummerer, M.; Turner, D.A. [Westinghouse Hanford Co., Richland, WA (United States); Plys, M.G. [Fauske and Associates, Inc., Burr Ridge, IL (United States)

1994-03-01T23:59:59.000Z

363

Ultrasonic liquid level detector  

DOE Patents [OSTI]

An ultrasonic liquid level detector for use within a shielded container, the detector being tubular in shape with a chamber at its lower end into which liquid from in the container may enter and exit, the chamber having an ultrasonic transmitter and receiver in its top wall and a reflector plate or target as its bottom wall whereby when liquid fills the chamber a complete medium is then present through which an ultrasonic wave may be transmitted and reflected from the target thus signaling that the liquid is at chamber level.

Kotz, Dennis M. (North Augusta, SC); Hinz, William R. (Augusta, GA)

2010-09-28T23:59:59.000Z

364

Method and compositions for the degradation of tributyl phosphate in chemical waste mixtures  

DOE Patents [OSTI]

A method and process are disclosed for the degradation of tributyl phosphate in an organic waste mixture and a biologically pure, novel bacteria culture for accomplishing the same. A newly-discovered bacteria (a strain of Acinetobacter sp. ATCC 55587) is provided which is combined in a reactor vessel with a liquid waste mixture containing tributyl phosphate and one or more organic waste compounds capable of functioning as growth substrates for the bacteria. The bacteria is thereafter allowed to incubate within the waste mixture. As a result, the tributyl phosphate and organic compounds within the waste mixture are metabolized (degraded) by the bacteria, thereby eliminating such materials which are environmentally hazardous. In addition, the bacteria is capable of degrading waste mixtures containing high quantities of tributyl phosphate (e.g. up to about 1.0% by weight tributyl phosphate). 6 figs.

Stoner, D.L.; Tien, A.J.

1995-09-26T23:59:59.000Z

365

Seafood processing waste management and its impact on local community in Cochin Corporation, India  

Science Journals Connector (OSTI)

This study utilised face to face survey method through semi structured interview schedule for gathering information regarding the quantity of seafood raw materials procured and the associated waste generation pattern, waste management issues and ultimately the impact excreted by the waste produced to the local community, in India's one of the major seafood processing zone, the Cochin Corporation (CC), in the state of Kerala. In the study area, large quantities of seafood solid waste is left as unutilised, and are managed largely by the private sector for disposal. The unregulated disposal of seafood solid and liquid waste has created environmental and social ill effects in the area. It is hoped that this study would prove as a tool for future waste management planning and by-product valorisation decisions by the seafood industry as well as the authorities.

Abhilash Sasidharan; K.K. Baiju; Saleena Mathew

2013-01-01T23:59:59.000Z

366

Determination of Radioisotope Content by Measurement of Waste Package Dose Rates - 13394  

SciTech Connect (OSTI)

The objective of this communication is to report the observed correlation between the calculated air kerma rates produced by radioactive waste drums containing untreated ion-exchange resin and activated charcoal slurries with the measured radiation field of each package. Air kerma rates at different distances from the drum surface were calculated with the activity concentrations previously determined by gamma spectrometry of waste samples and the estimated mass, volume and geometry of solid and liquid phases of each waste package. The water content of each waste drum varies widely between different packages. Results will allow determining the total activity of wastes and are intended to complete the previous steps taken to characterize the radioisotope content of wastes packages. (authors)

Souza, Daiane Cristini B.; Gimenes Tessaro, Ana Paula; Vicente, Roberto [Nuclear and Energy Research Institute Brazil, Radioactive Waste Management Department IPEN/GRR, Sao Paulo. SP. (Brazil)] [Nuclear and Energy Research Institute Brazil, Radioactive Waste Management Department IPEN/GRR, Sao Paulo. SP. (Brazil)

2013-07-01T23:59:59.000Z

367

Process for recovery of palladium from nuclear fuel reprocessing wastes  

DOE Patents [OSTI]

Palladium is selectively removed from spent nuclear fuel reprocessing waste by adding sugar to a strong nitric acid solution of the waste to partially denitrate the solution and cause formation of an insoluble palladium compound. The process includes the steps of: (a) adjusting the nitric acid content of the starting solution to about 10 M; (b) adding 50% sucrose solution in an amount sufficient to effect the precipitation of the palladium compound; (c) heating the solution at reflux temperature until precipitation is complete; and (d) centrifuging the solution to separate the precipitated palladium compound from the supernatant liquid.

Campbell, D.O.; Buxton, S.R.

1980-06-16T23:59:59.000Z

368

Two-stage thermal/nonthermal waste treatment process  

SciTech Connect (OSTI)

An innovative waste treatment technology is being developed in Los Alamos to address the destruction of hazardous organic wastes. The technology described in this report uses two stages: a packed bed reactor (PBR) in the first stage to volatilize and/or combust liquid organics and a silent discharge plasma (SDP) reactor to remove entrained hazardous compounds in the off-gas to even lower levels. We have constructed pre-pilot-scale PBR-SDP apparatus and tested the two stages separately and in combined modes. These tests are described in the report.

Rosocha, L.A.; Anderson, G.K.; Coogan, J.J.; Kang, M.; Tennant, R.A.; Wantuck, P.J.

1993-05-01T23:59:59.000Z

369

Hanford Waste Vitrification Plant technical manual  

SciTech Connect (OSTI)

A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version.

Larson, D.E. [ed.; Watrous, R.A.; Kruger, O.L. [and others

1996-03-01T23:59:59.000Z

370

LIQUID AIR INTERFACE CORROSION TESTING FOR FY2010  

SciTech Connect (OSTI)

An experimental study was undertaken to investigate the corrosivity to carbon steel of the liquid-air interface of dilute simulated radioactive waste solutions. Open-circuit potentials were measured on ASTM A537 carbon steel specimens located slightly above, at, and below the liquid-air interface of simulated waste solutions. The 0.12-inch-diameter specimens used in the study were sized to respond to the assumed distinctive chemical environment of the liquid-air interface, where localized corrosion in poorly inhibited solutions may frequently be observed. The practical inhibition of such localized corrosion in liquid radioactive waste storage tanks is based on empirical testing and a model of a liquid-air interface environment that is made more corrosive than the underlying bulk liquid due to chemical changes brought about by absorbed atmospheric carbon dioxide. The chemical changes were assumed to create a more corrosive open-circuit potential in carbon in contact with the liquid-air interface. Arrays of 4 small specimens spaced about 0.3 in. apart were partially immersed so that one specimen contacted the top of the meniscus of the test solution. Two specimens contacted the bulk liquid below the meniscus and one specimen was positioned in the vapor space above the meniscus. Measurements were carried out for up to 16 hours to ensure steady-state had been obtained. The results showed that there was no significant difference in open-circuit potentials between the meniscus-contact specimens and the bulk-liquid-contact specimens. With the measurement technique employed, no difference was detected between the electrochemical conditions of the meniscus versus the bulk liquid. Stable open-circuit potentials were measured on the specimen located in the vapor space above the meniscus, showing that there existed an electrochemical connection through a thin film of solution extending up from the meniscus. This observation supports the Hobbs-Wallace model of the development of the pitting susceptibility of carbon steel in alkaline solutions.

Zapp, P.

2010-12-16T23:59:59.000Z

371

Quality Services: Solid Wastes, Part 360: Solid Waste Management Facilities  

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

0: Solid Waste Management 0: Solid Waste Management Facilities (New York) Quality Services: Solid Wastes, Part 360: Solid Waste Management Facilities (New York) < Back Eligibility Agricultural Commercial Fuel Distributor Industrial Institutional Investor-Owned Utility Multi-Family Residential Municipal/Public Utility Rural Electric Cooperative Transportation Utility Program Info State New York Program Type Environmental Regulations Provider NY Department of Environmental Conservation These regulations apply to all solid wastes with the exception of hazardous or radioactive waste. Proposed solid waste processing facilities are required to obtain permits prior to construction, and the regulations provide details about permitting, construction, registration, and operation requirements. The regulations contain specific guidance for land

372

TRU Waste Sampling Program: Volume I. Waste characterization  

SciTech Connect (OSTI)

Volume I of the TRU Waste Sampling Program report presents the waste characterization information obtained from sampling and characterizing various aged transuranic waste retrieved from storage at the Idaho National Engineering Laboratory and the Los Alamos National Laboratory. The data contained in this report include the results of gas sampling and gas generation, radiographic examinations, waste visual examination results, and waste compliance with the Waste Isolation Pilot Plant-Waste Acceptance Criteria (WIPP-WAC). A separate report, Volume II, contains data from the gas generation studies.

Clements, T.L. Jr.; Kudera, D.E.

1985-09-01T23:59:59.000Z

373

Hanford Tank Waste Residuals  

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

Hanford Hanford Tank Waste Residuals DOE HLW Corporate Board November 6, 2008 Chris Kemp, DOE ORP Bill Hewitt, YAHSGS LLC Hanford Tanks & Tank Waste * Single-Shell Tanks (SSTs) - ~27 million gallons of waste* - 149 SSTs located in 12 SST Farms - Grouped into 7 Waste Management Areas (WMAs) for RCRA closure purposes: 200 West Area S/SX T TX/TY U 200 East Area A/AX B/BX/BY C * Double-Shell Tanks (DSTs) - ~26 million gallons of waste* - 28 DSTs located in 6 DST Farms (1 West/5 East) * 17 Misc Underground Storage Tanks (MUST) * 43 Inactive MUST (IMUST) 200 East Area A/AX B/BX/BY C * Volumes fluctuate as SST retrievals and 242-A Evaporator runs occur. Major Regulatory Drivers * Radioactive Tank Waste Materials - Atomic Energy Act - DOE M 435.1-1, Ch II, HLW - Other DOE Orders * Hazardous/Dangerous Tank Wastes - Hanford Federal Facility Agreement and Consent Order (TPA) - Retrieval/Closure under State's implementation

374

Waste inspection tomography (WIT)  

SciTech Connect (OSTI)

The WIT program will provide an inspection system that offers the nuclear waste evaluator a unique combination of tools for regulatory-driven characterization of low-level waste (LLW), transuranic waste (TRU), and mixed waste drums. WIT provides nondestructive, noninvasive, and environmentally safe inspections using X-ray and gamma ray technologies, with reasonable cost and throughput. Two emission imaging techniques will be employed for characterizing materials in waste containers. The first of these is gamma emission tomography, commonly called single-photon emission computed tomography (SPECT). Rather than using an external radiation source, SPECT uses the emission of radioactive materials within the object of interest for imaging. In this case, emission from actual nuclear waste within a container will provide a three-dimensional image of the radioactive substances in the container. The second emission technique will use high-purity germanium detectors for gamma ray spectroscopy. This technique, called nondestructive assay (NDA), can identify the emitting isotopic species and strength. Work in emission tomography and assay of nuclear waste has been undertaken at Lawrence Livermore National Laboratory using a technique called Passive Tomography. Results from a process development unit are presented.

Bernardi, R.T.; Han, K.S.

1994-12-31T23:59:59.000Z

375

Effects of simulant mixed waste on EPDM and butyl rubber  

SciTech Connect (OSTI)

The authors have developed a Chemical Compatibility Testing Program for the evaluation of plastic packaging components which may be used in transporting mixed waste forms. In this program, they have screened 10 plastic materials in four liquid mixed waste simulants. These plastics were butadiene-acrylonitrile copolymer (Nitrile) rubber, cross-linked polyethylene, epichlorohydrin rubber, ethylene-propylene (EPDM) rubber, fluorocarbons (Viton and Kel-F{trademark}), polytetrafluoro-ethylene (Teflon), high-density polyethylene, isobutylene-isoprene copolymer (Butyl) rubber, polypropylene, and styrene-butadiene (SBR) rubber. The selected simulant mixed wastes were (1) an aqueous alkaline mixture of sodium nitrate and sodium nitrite; (2) a chlorinated hydrocarbon mixture; (3) a simulant liquid scintillation fluid; and (4) a mixture of ketones. The screening testing protocol involved exposing the respective materials to approximately 3 kGy of gamma radiation followed by 14-day exposures to the waste simulants at 60 C. The rubber materials or elastomers were tested using Vapor Transport Rate measurements while the liner materials were tested using specific gravity as a metric. The authors have developed a chemical compatibility program for the evaluation of plastic packaging components which may be incorporated in packaging for transporting mixed waste forms. From the data analyses performed to date, they have identified the thermoplastic, polychlorotrifluoroethylene, as having the greatest chemical compatibility after having been exposed to gamma radiation followed by exposure to the Hanford Tank simulant mixed waste. The most striking observation from this study was the poor performance of polytetrafluoroethylene under these conditions. In the evaluation of the two elastomeric materials they have concluded that while both materials exhibit remarkable resistance to these environmental conditions, EPDM has a greater resistance to this corrosive simulant mixed waste.

Nigrey, P.J.; Dickens, T.G.

1997-11-01T23:59:59.000Z

376

Separation, Concentration, and Immobilization of Technetium and Iodine from Alkaline Supernate Waste  

SciTech Connect (OSTI)

Development of remediation technologies for the characterization, retrieval, treatment, concentration, and final disposal of radioactive and chemical tank waste stored within the Department of Energy (DOE) complex represents an enormous scientific and technological challenge. A combined total of over 90 million gallons of high-level waste (HLW) and low-level waste (LLW) are stored in 335 underground storage tanks at four different DOE sites. Roughly 98% of this waste is highly alkaline in nature and contains high concentrations of nitrate and nitrite salts along with lesser concentrations of other salts. The primary waste forms are sludge, saltcake, and liquid supernatant with the bulk of the radioactivity contained in the sludge, making it the largest source of HLW. The saltcake (liquid waste with most of the water removed) and liquid supernatant consist mainly of sodium nitrate and sodium hydroxide salts. The main radioactive constituent in the alkaline supernatant is cesium-137, but strontium-90, technetium-99, and transuranic nuclides are also present in varying concentrations. Reduction of the radioactivity below Nuclear Regulatory Commission (NRC) limits would allow the bulk of the waste to be disposed of as LLW. Because of the long half-life of technetium-99 (2.1 x 10 5 y) and the mobility of the pertechnetate ion (TcO 4 - ) in the environment, it is expected that technetium will have to be removed from the Hanford wastes prior to disposal as LLW. Also, for some of the wastes, some level of technetium removal will be required to meet LLW criteria for radioactive content. Therefore, DOE has identified a need to develop technologies for the separation and concentration of technetium-99 from LLW streams. Eichrom has responded to this DOE-identified need by demonstrating a complete flowsheet for the separation, concentration, and immobilization of technetium (and iodine) from alkaline supernatant waste.

James Harvey; Michael Gula

1998-12-07T23:59:59.000Z

377

Waste Isolation Pilot Plant 2003 Site Environmental Report  

SciTech Connect (OSTI)

The purpose of this report is to provide information needed by the DOE to assess WIPP's environmental performance and to convey that performance to stakeholders and members of the public. This report has been prepared in accordance with DOE Order 231.1A and DOE guidance. This report documents WIPP's environmental monitoring programs and their results for 2003. The WIPP Project is authorized by the DOE National Security and Military Applications of Nuclear Energy Authorization Act of 1980 (Pub. L. 96-164). After more than 20 years of scientific study and public input, WIPP received its first shipment of waste on March 26, 1999. Located in southeastern New Mexico, WIPP is the nation's first underground repository permitted to safely and permanently dispose of TRU radioactive and mixed waste (as defined in the WIPP LWA) generated through the research and production of nuclear weapons and other activities related to the national defense of the United States. TRU waste is defined in the WIPP LWA as radioactive waste containing more than 100 nanocuries (3,700 becquerels [Bq]) of alpha-emitting transuranic isotopes per gram of waste, with half-lives greater than 20 years. Exceptions are noted as high-level waste, waste that has been determined not to require the degree of isolation required by the disposal regulations, and waste the U.S. Nuclear Regulatory Commission (NRC) has approved for disposal. Most TRU waste is contaminated industrial trash, such as rags and old tools, and sludges from solidified liquids; glass; metal; and other materials from dismantled buildings. A TRU waste is eligible for disposal at WIPP if it has been generated in whole or in partby one or more of the activities listed in the Nuclear Waste Policy Act of 1982 (42 United States Code [U.S.C.] 10101, et seq.), including naval reactors development, weapons activities, verification and control technology, defense nuclear materials production, defense nuclear waste and materials by-products management, defense nuclear materials security and safeguards and security investigations, and defense research and development. The waste must also meet the WIPP Waste Acceptance Criteria. When TRU waste arrives at WIPP, it is transported into the Waste Handling Building. The waste containers are removed from the shipping containers, placed on the waste hoist, and lowered to the repository level of 655 m (2,150 ft; approximately 0.5 mi) below the surface. Next, the containers of waste are removed from the hoist and placed in excavated storage rooms in the Salado Formation, a thick sequence of evaporite beds deposited approximately 250 million years ago (Figure 1.1). After each panel has been filled with waste, specially designed closures are emplaced. When all of WIPP's panels have been filled, at the conclusion of WIPP operations, seals will be placed in the shafts. Salt under pressure is relatively plastic, and mine openings will be allowed to creep closed for final disposal, encapsulating and isolating the waste.

Washington Regulatory and Environmental Services

2005-09-03T23:59:59.000Z

378

Radioactive waste material disposal  

DOE Patents [OSTI]

The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide. 3 figs.

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

1995-10-24T23:59:59.000Z

379

Radioactive waste material disposal  

DOE Patents [OSTI]

The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide.

Forsberg, Charles W. (155 Newport Dr., Oak Ridge, TN 37830); Beahm, Edward C. (106 Cooper Cir., Oak Ridge, TN 37830); Parker, George W. (321 Dominion Cir., Knoxville, TN 37922)

1995-01-01T23:59:59.000Z

380

Carbon monoxide absorbing liquid  

SciTech Connect (OSTI)

The present disclosure is directed to a carbon monoxide absorbing liquid containing a cuprous ion, hydrochloric acid and titanum trichloride. Titanium trichloride is effective in increasing the carbon monoxide absorption quantity. Furthermore, titanium trichloride remarkably increases the oxygen resistance. Therefore, this absorbing liquid can be used continuously and for a long time.

Arikawa, Y.; Horigome, S.; Kanehori, K.; Katsumoto, M.

1981-07-07T23:59:59.000Z

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Precision liquid level sensor  

DOE Patents [OSTI]

A precision liquid level sensor utilizes a balanced R. F. bridge, each arm including an air dielectric line. Changes in liquid level along one air dielectric line imbalance the bridge and create a voltage which is directly measurable across the bridge.

Field, Michael E. (Albuquerque, NM); Sullivan, William H. (Albuquerque, NM)

1985-01-01T23:59:59.000Z

382

Hazardous Waste Disposal Sites (Iowa)  

Broader source: Energy.gov [DOE]

These sections contain information on fees and monitoring relevant to operators of hazardous waste disposal sites.

383

Generating power with waste wood  

SciTech Connect (OSTI)

Among the biomass renewables, waste wood has great potential with environmental and economic benefits highlighting its resume. The topics of this article include alternate waste wood fuel streams; combustion benefits; waste wood comparisons; waste wood ash; pilot scale tests; full-scale test data; permitting difficulties; and future needs.

Atkins, R.S.

1995-02-01T23:59:59.000Z

384

Methane generation from waste materials  

DOE Patents [OSTI]

An organic solid waste digester for producing methane from solid waste, the digester comprising a reactor vessel for holding solid waste, a sprinkler system for distributing water, bacteria, and nutrients over and through the solid waste, and a drainage system for capturing leachate that is then recirculated through the sprinkler system.

Samani, Zohrab A. (Las Cruces, NM); Hanson, Adrian T. (Las Cruces, NM); Macias-Corral, Maritza (Las Cruces, NM)

2010-03-23T23:59:59.000Z

385

Integrated High-Level Waste System Planning - Utilizing an Integrated Systems Planning Approach to Ensure End-State Definitions are Met and Executed - 13244  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is a Department of Energy site which has produced nuclear materials for national defense, research, space, and medical programs since the 1950's. As a by-product of this activity, approximately 37 million gallons of high-level liquid waste containing approximately 292 million curies of radioactivity is stored on an interim basis in 45 underground storage tanks. Originally, 51 tanks were constructed and utilized to support the mission. Four tanks have been closed and taken out of service and two are currently undergoing the closure process. The Liquid Waste System is a highly integrated operation involving safely storing liquid waste in underground storage tanks; removing, treating, and dispositioning the low-level waste fraction in grout; vitrifying the higher activity waste at the Defense Waste Processing Facility; and storing the vitrified waste in stainless steel canisters until permanent disposition. After waste removal and processing, the storage and processing facilities are decontaminated and closed. A Liquid Waste System Plan (hereinafter referred to as the Plan) was developed to integrate and document the activities required to disposition legacy and future High-Level Waste and to remove from service radioactive liquid waste tanks and facilities. It establishes and records a planning basis for waste processing in the liquid waste system through the end of the program mission. The integrated Plan which recognizes the challenges of constrained funding provides a path forward to complete the liquid waste mission within all regulatory and legal requirements. The overarching objective of the Plan is to meet all Federal Facility Agreement and Site Treatment Plan regulatory commitments on or ahead of schedule while preserving as much life cycle acceleration as possible through incorporation of numerous cost savings initiatives, elimination of non-essential scope, and deferral of other scope not on the critical path to compliance. There is currently a premium on processing and storage space in the radioactive liquid waste tank system. To enable continuation of risk reduction initiatives, the Plan establishes a processing strategy that provides tank space required to meet, or minimizes the impacts to meeting, programmatic objectives. The Plan also addresses perturbations in funding and schedule impacts. (authors)

Ling, Lawrence T. [URS-Savannah River Remediation, Savannah River Site, Building 766-H Room 2205, Aiken, SC 29808 (United States)] [URS-Savannah River Remediation, Savannah River Site, Building 766-H Room 2205, Aiken, SC 29808 (United States); Chew, David P. [URS-Savannah River Remediation, Savannah River Site, Building 766-H Room 2426, Aiken, SC 29808 (United States)] [URS-Savannah River Remediation, Savannah River Site, Building 766-H Room 2426, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

386

Certification Plan, low-level waste Hazardous Waste Handling Facility  

SciTech Connect (OSTI)

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan also incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. This plan provides guidance from the HWHF to waste generators, waste handlers, and the Waste Certification Specialist to enable them to conduct their activities and carry out their responsibilities in a manner that complies with the requirements of WHC-WAC. Waste generators have the primary responsibility for the proper characterization of LLW. The Waste Certification Specialist verifies and certifies that LBL LLW is characterized, handled, and shipped in accordance with the requirements of WHC-WAC. Certification is the governing process in which LBL personnel conduct their waste generating and waste handling activities in such a manner that the Waste Certification Specialist can verify that the requirements of WHC-WAC are met.

Albert, R.

1992-06-30T23:59:59.000Z

387

Liquid Fuels Market Module  

U.S. Energy Information Administration (EIA) Indexed Site

Liquid Fuels Market Module Liquid Fuels Market Module This page inTenTionally lefT blank 145 U.S. Energy Information Administration | Assumptions to the Annual Energy Outlook 2013 Liquid Fuels Market Module The NEMS Liquid Fuels Market Module (LFMM) projects petroleum product prices and sources of supply for meeting petroleum product demand. The sources of supply include crude oil (both domestic and imported), petroleum product imports, unfinished oil imports, other refinery inputs (including alcohols, ethers, esters, corn, biomass, and coal), natural gas plant liquids production, and refinery processing gain. In addition, the LFMM projects capacity expansion and fuel consumption at domestic refineries. The LFMM contains a linear programming (LP) representation of U.S. petroleum refining

388

Reading Comprehension - Liquid Nitrogen  

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

Liquid Nitrogen Liquid Nitrogen Nitrogen is the most common substance in Earth's _________ crust oceans atmosphere trees . In the Earth's atmosphere, nitrogen is a gas. The particles of a gas move very quickly. They run around and bounce into everyone and everything. The hotter a gas is, the _________ slower faster hotter colder the particles move. When a gas is _________ cooled warmed heated compressed , its particles slow down. If a gas is cooled enough, it can change from a gas to a liquid. For nitrogen, this happens at a very _________ strange warm low high temperature. If you want to change nitrogen from a gas to a liquid, you have to bring its temperature down to 77 Kelvin. That's 321 degrees below zero _________ Kelvin Celsius Centigrade Fahrenheit ! Liquid nitrogen looks like water, but it acts very differently. It

389

Tank Waste Strategy Update  

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

Tank Waste Subcommittee www.em.doe.gov safety performance cleanup closure E M Environmental Management 1 Tank Waste Subcommittee Ken Picha Office of Environmental Management December 5, 2011 Background Tank Waste Subcommittee (TWS)originally chartered, in response to Secretary's request to perform a technical review of Waste Treatment and Immobilization Plant (WTP) in May 2010. Three tasks: o Verification of closure of WTP External Flowsheet Review Team (EFRT) issues. o WTP Technical Design Review o WTP potential improvements Report completed and briefed to DOE in September 2010 www.em.doe.gov safety performance cleanup closure E M Environmental Management 2 Report completed and briefed to DOE in September 2010 Follow-on scope for TWS identified immediately after briefing to DOE and

390

Waste Treatment Plant Overview  

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

Hanford Site, located in southeastern Washington state, Hanford Site, located in southeastern Washington state, was the largest of three defense production sites in the U.S. Over the span of 40 years, it was used to produce 64 metric tons of plutonium, helping end World War II and playing a major role in military defense efforts during the Cold War. As a result, 56 million gallons of radioactive and chemical wastes are now stored in 177 underground tanks on the Hanford Site. To address this challenge, the U.S. Department of Energy 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 "Vit Plant," will use vitrification to immobilize most of Hanford's dangerous tank waste.

391

Waste Steam Recovery  

E-Print Network [OSTI]

An examination has been made of the recovery of waste steam by three techniques: direct heat exchange to process, mechanical compression, and thermocompression. Near atmospheric steam sources were considered, but the techniques developed are equally...

Kleinfeld, J. M.

1979-01-01T23:59:59.000Z

392

Waste and Recycling  

ScienceCinema (OSTI)

Nuclear engineer Dr. Kathy McCarthy talks about nuclear energy, the challenge of nuclear waste and the research aimed at solutions. For more information about nuclear energy research, visit http://www.facebook.com/idahonationallaboratory.

McCarthy, Kathy

2013-05-28T23:59:59.000Z

393

Technological options for management of hazardous wastes from US Department of Energy facilities  

SciTech Connect (OSTI)

This report provides comprehensive information on the technological options for management of hazardous wastes generated at facilities owned or operated by the US Department of Energy (DOE). These facilities annually generate a large quantity of wastes that could be deemed hazardous under the Resource Conservation and Recovery Act (RCRA). Included in these wastes are liquids or solids containing polychlorinated biphenyls, pesticides, heavy metals, waste oils, spent solvents, acids, bases, carcinogens, and numerous other pollutants. Some of these wastes consist of nonnuclear hazardous chemicals; others are mixed wastes containing radioactive materials and hazardous chemicals. Nearly 20 unit processes and disposal methods are presented in this report. They were selected on the basis of their proven utility in waste management and potential applicability at DOE sites. These technological options fall into five categories: physical processes, chemical processes, waste exchange, fixation, and ultimate disposal. The options can be employed for either resource recovery, waste detoxification, volume reduction, or perpetual storage. Detailed descriptions of each technological option are presented, including information on process performance, cost, energy and environmental considerations, waste management of applications, and potential applications at DOE sites. 131 references, 25 figures, 23 tables.

Chiu, S.; Newsom, D.; Barisas, S.; Humphrey, J.; Fradkin, L.; Surles, T.

1982-08-01T23:59:59.000Z

394

Citrus Waste Biomass Program  

SciTech Connect (OSTI)

Renewable Spirits is developing an innovative pilot plant bio-refinery to establish the commercial viability of ehtanol production utilizing a processing waste from citrus juice production. A novel process based on enzymatic hydrolysis of citrus processing waste and fermentation of resulting sugars to ethanol by yeasts was successfully developed in collaboration with a CRADA partner, USDA/ARS Citrus and Subtropical Products Laboratory. The process was also successfully scaled up from laboratory scale to 10,000 gal fermentor level.

Karel Grohman; Scott Stevenson

2007-01-30T23:59:59.000Z

395

Air Liquide - Biogas & Fuel Cells  

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

Liquide - Biogas & Fuel Cells Hydrogen Energy Biogas Upgrading Technology 12 June 2012 Charlie.Anderson@airliquide.com 2 Air Liquide, world leader in gases for industry,...

396

Sandia National Laboratories: ionic liquid  

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

liquid Biofuels Blend Right In: Researchers Show Ionic Liquids Effective for Pretreating Mixed Blends of Biofuel Feedstocks On February 26, 2013, in Biofuels, Biomass, Energy,...

397

Method for extracting metals from aqueous waste streams for long term storage  

DOE Patents [OSTI]

A liquid--liquid extraction method for removing metals and hydrous metal colloids from waste streams is provided wherein said waste streams are contacted with a solvent system containing a water-in-oil microemulsion wherein the inverted micelles contain the extracted metal. A silicon alkoxide, either alone or in combination with other metal alkoxide compounds is added to the water-in-oil microemulsion, thereby allowing encapsulation of the extracted metal within a silicon oxide network. Lastly, the now-encapsulated metal is precipitated from the water-in-oil microemulsion phase to yield aggregates of metal-silicate particles having average individual particle sizes of approximately 40 nanometers.

Chaiko, David J. (Woodridge, IL)

1995-01-01T23:59:59.000Z

398

Modelling and Numerical Simulation of Gas Migration in a Nuclear Waste Repository  

E-Print Network [OSTI]

We present a compositional compressible two-phase, liquid and gas, flow model for numerical simulations of hydrogen migration in deep geological radioactive waste repository. This model includes capillary effects and the gas diffusivity. The choice of the main variables in this model, Total or Dissolved Hydrogen Mass Concentration and Liquid Pressure, leads to a unique and consistent formulation of the gas phase appearance and disappearance. After introducing this model, we show computational evidences of its adequacy to simulate gas phase appearance and disappearance in different situations typical of underground radioactive waste repository.

Bourgeat, Alain; Smai, Farid

2010-01-01T23:59:59.000Z

399

Method for extracting metals from aqueous waste streams for long term storage  

DOE Patents [OSTI]

A liquid-liquid extraction method for removing metals and hydrous metal colloids from waste streams is provided wherein said waste streams are contacted with a solvent system containing a water-in-oil microemulsion wherein the inverted micelles contain the extracted metal. A silicon alkoxide, either alone or in combination with other metal alkoxide compounds is added to the water-in-oil microemulsion, thereby allowing encapsulation of the extracted metal within a silicon oxide network. Lastly, the now-encapsulated metal is precipitated from the water-in-oil microemulsion phase to yield aggregates of metal-silicate particles having average. individual particle sizes of approximately 40 manometers.

Chaiko, D.J.

1993-01-01T23:59:59.000Z

400

Alternate Fuels: Is Your Waste Stream a Fuel Source?  

E-Print Network [OSTI]

in their boiler systems. And, the trend toward using Process Gases, Flammable Liquids, and Volatile Organic Compounds (\\iDe's), to supplement fossil fuels, will be considered a key element of the management strategy for industrial power plants. The increase...ALTERNATE FUELS: IS YOUR WASTE STREAM A FUEL SOURCE? PHn, COERPER. MANAGER ALTERNATE FUEL SYSTEMS. CLEAVER-BROOKS. Mn,WAUKEE. WI ABSTRACT Before the year 2000. more than one quarter of u.s. businesses will be firing Alternate Fuels...

Coerper, P.

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Liquid sampling system  

DOE Patents [OSTI]

A conduit extends from a reservoir through a sampling station and back to the reservoir in a closed loop. A jet ejector in the conduit establishes suction for withdrawing liquid from the reservoir. The conduit has a self-healing septum therein upstream of the jet ejector for receiving one end of a double-ended cannula, the other end of which is received in a serum bottle for sample collection. Gas is introduced into the conduit at a gas bleed between the sample collection bottle and the reservoir. The jet ejector evacuates gas from the conduit and the bottle and aspirates a column of liquid from the reservoir at a high rate. When the withdrawn liquid reaches the jet ejector the rate of flow therethrough reduces substantially and the gas bleed increases the pressure in the conduit for driving liquid into the sample bottle, the gas bleed forming a column of gas behind the withdrawn liquid column and interrupting the withdrawal of liquid from the reservoir. In the case of hazardous and toxic liquids, the sample bottle and the jet ejector may be isolated from the reservoir and may be further isolated from a control station containing remote manipulation means for the sample bottle and control valves for the jet ejector and gas bleed. 5 figs.

Larson, L.L.

1984-09-17T23:59:59.000Z

402

Liquid sampling system  

DOE Patents [OSTI]

A conduit extends from a reservoir through a sampling station and back to the reservoir in a closed loop. A jet ejector in the conduit establishes suction for withdrawing liquid from the reservoir. The conduit has a self-healing septum therein upstream of the jet ejector for receiving one end of a double-ended cannula, the other end of which is received in a serum bottle for sample collection. Gas is introduced into the conduit at a gas bleed between the sample collection bottle and the reservoir. The jet ejector evacuates gas from the conduit and the bottle and aspirates a column of liquid from the reservoir at a high rate. When the withdrawn liquid reaches the jet ejector the rate of flow therethrough reduces substantially and the gas bleed increases the pressure in the conduit for driving liquid into the sample bottle, the gas bleed forming a column of gas behind the withdrawn liquid column and interrupting the withdrawal of liquid from the reservoir. In the case of hazardous and toxic liquids, the sample bottle and the jet ejector may be isolated from the reservoir and may be further isolated from a control station containing remote manipulation means for the sample bottle and control valves for the jet ejector and gas bleed.

Larson, Loren L. (Idaho Falls, ID)

1987-01-01T23:59:59.000Z

403

Tank Waste Committee Page 1  

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

have had as much pumpable liquid removed as practicable (the liquid that can leak through liners and reach soils). Jeff reviewed the inventory of technetium-99 and nitrate,...

404

Liquid-level detector  

DOE Patents [OSTI]

Aliquid level sensor is described which has a pair of upright conductors spaced by an insulator defining a first high resistance path between the conductors. An electrically conductive path is interposed between the upright conductors at a discrete location at which liquid level is to be measured. It includes a liquid accessible gap of a dimension such that the electrical resistance across the conductor when the gap is filled with the liquid is detectably less than when the gap is emptied. The conductor might also be physically altered by temperature changes to serve also as an indicator of elevated temperature.

Not Available

1981-01-29T23:59:59.000Z

405

Liquid metal electric pump  

DOE Patents [OSTI]

An electrical pump for pumping liquid metals to high pressures in high temperature environments without the use of magnets or moving mechanical parts. The pump employs a non-porous solid electrolyte membrane, typically ceramic, specific to the liquid metal to be pumped. A DC voltage is applied across the thickness of the membrane causing ions to form and enter the membrane on the electrically positive surface, with the ions being neutralized on the opposite surface. This action provides pumping of the liquid metal from one side of the non-porous solid electrolyte membrane to the other. 3 figs.

Abbin, J.P.; Andraka, C.E.; Lukens, L.L.; Moreno, J.B.

1992-01-14T23:59:59.000Z

406

Independent Activity Report, Hanford Waste Treatment Plant -...  

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

Waste Treatment Plant - February 2011 Independent Activity Report, Hanford Waste Treatment Plant - February 2011 February 2011 Hanford Waste Treatment Plant Construction Quality...

407

Rhenium solubility in borosilicate nuclear waste glass  

E-Print Network [OSTI]

Glasses Developed for Nuclear Waste Immobilization," 91[12],solubility in borosilicate nuclear waste glass Ashutoshfor the researchers in nuclear waste community around the

McCloy, John S.

2014-01-01T23:59:59.000Z

408

Municipal Solid Waste | Open Energy Information  

Open Energy Info (EERE)

Waste Jump to: navigation, search TODO: Add description List of Municipal Solid Waste Incentives Retrieved from "http:en.openei.orgwindex.php?titleMunicipalSolidWaste&oldid...

409

Waste Processing Annual Technology Development Report 2007 |...  

Office of Environmental Management (EM)

Waste Processing Annual Technology Development Report 2007 Waste Processing Annual Technology Development Report 2007 Waste Processing Annual Technology Development Report 2007...

410

Pollution Prevention, Waste Reduction, and Recycling | Department...  

Office of Environmental Management (EM)

Pollution Prevention, Waste Reduction, and Recycling Pollution Prevention, Waste Reduction, and Recycling The Pollution Prevention, Waste Reduction and Recycling Program was...

411

Waste Isolation Pilot Plant | Department of Energy  

Office of Environmental Management (EM)

Waste Isolation Pilot Plant Waste Isolation Pilot Plant Operators prepare drums of contact-handled transuranic waste for loading into transportation containers Operators prepare...

412

Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania)  

Open Energy Info (EERE)

Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) No revision has been approved for this page. It is currently under review by our subject matter experts. Jump to: navigation, search Last modified on February 13, 2013. EZFeed Policy Place Pennsylvania Name Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Policy Category Other Policy Policy Type Environmental Regulations Affected Technologies Biomass/Biogas, Coal with CCS, Concentrating Solar Power, Energy Storage, Fuel Cells, Geothermal Electric, Hydroelectric, Hydroelectric (Small), Natural Gas, Nuclear, Solar Photovoltaics, Wind energy Active Policy Yes Implementing Sector State/Province Program Administrator Pennsylvania Department of Environmental Protection

413

Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania)  

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

Municipal Waste Planning, Recycling and Waste Reduction Act Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Pennsylvania Program Type Environmental Regulations

414

SECONDARY WASTE MANAGEMENT STRATEGY FOR EARLY LOW ACTIVITY WASTE TREATMENT  

SciTech Connect (OSTI)

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.

CRAWFORD TW

2008-07-17T23:59:59.000Z

415

Energy from waste via coal/waste co-firing  

SciTech Connect (OSTI)

The paper reviews the feasibility of waste-to-energy plants using the cocombustion of coal with refuse-derived fuels. The paper discusses the types of wastes available: municipal solid wastes, plastics, tires, biomass, and specialized industrial wastes, such as waste oils, post-consumer carpet, auto shredder residues, and petroleum coke. The five most common combustion systems used in co-firing are briefly described. They are the stoker boiler, suspension-fired boilers, cyclone furnaces, fluidized bed boilers, and cement kilns. The paper also discusses the economic incentives for generating electricity from waste.

Winslow, J.; Ekmann, J.; Smouse, S. [Dept. of Energy, Pittsburgh, PA (United States). Pittsburgh Energy Technology Center; Ramezan, M. [Burns and Roe Services Corp., Pittsburgh, PA (United States); Harding, S.

1996-12-31T23:59:59.000Z

416

Solid Waste and Infectious Waste Regulations (Ohio) | Department of Energy  

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

and Infectious Waste Regulations (Ohio) and Infectious Waste Regulations (Ohio) Solid Waste and Infectious Waste Regulations (Ohio) < Back Eligibility Utility Agricultural Investor-Owned Utility Industrial Municipal/Public Utility Local Government Rural Electric Cooperative Program Info State Ohio Program Type Environmental Regulations Provider Ohio Environmental Protection Agency This chapter of the law that establishes the Ohio Environmental Protection Agency establishes the rules and regulations regarding solid waste. The chapter establishes specific regulations for biomass facilities, which includes permitting, siting, operation, safety guidelines, and closing requirements. Siting regulations include setbacks from waste handling areas for state facilities (1000 feet from jails, schools), requirements for not siting

417

Production of methane gas from organic fraction municipal solid waste (OFMSW) via anaerobic process: application methodology for the Malaysian condition  

Science Journals Connector (OSTI)

Solid waste management in Malaysia is confronted with many problems, including low collection coverage, irregular collection services, inadequate equipment used for waste collection, crude open dumping and burning without air and water pollution control systems, inadequate legal provisions and resource constraints. These problems have various effects on the development of the solid waste management system in Malaysia. Anaerobic digestion has been suggested as an alternative method for removing high concentrations of organic waste. In this study, two types of anaerobic digesters which are Simulated Landfill Bioreactor (SLBR) and Anaerobic Solid-Liquid (ASL) reactor were proposed. The reactors were operated at a temperature 60C, analysed for biogas production and volatile fatty acid.

Irnis Azura Zakarya; Ismail Abustan; Norli Ismail; Mohd Suffian Yusoff

2013-01-01T23:59:59.000Z

418

Waste Heat Management Options: Industrial Process Heating Systems  

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

Heat Management Options Heat Management Options Industrial Process Heating Systems By Dr. Arvind C. Thekdi E-mail: athekdi@e3minc.com E3M, Inc. August 20, 2009 2 Source of Waste Heat in Industries * Steam Generation * Fluid Heating * Calcining * Drying * Heat Treating * Metal Heating * Metal and Non-metal Melting * Smelting, agglomeration etc. * Curing and Forming * Other Heating Waste heat is everywhere! Arvind Thekdi, E3M Inc Arvind Thekdi, E3M Inc 3 Waste Heat Sources from Process Heating Equipment * Hot gases - combustion products - Temperature from 300 deg. F. to 3000 deg.F. * Radiation-Convection heat loss - From temperature source of 500 deg. F. to 2500 deg. F. * Sensible-latent heat in heated product - From temperature 400 deg. F. to 2200 deg. F. * Cooling water or other liquids - Temperature from 100 deg. F. to 180 deg. F.

419

LANL reaches waste shipment milestone  

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

LANL reaches waste shipment milestone LANL reaches waste shipment milestone LANL reaches waste shipment milestone The Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total. May 31, 2011 A shipment of transuranic waste on its way to the WIPP repository A shipment of transuranic waste on its way to the WIPP repository. Contact Fred deSousa Communicatons Office (505) 665-3430 Email LOS ALAMOS, New Mexico, May 31, 2011 - Los Alamos National Laboratory has reached an important milestone in its campaign to ship transuranic (TRU) waste from Cold War-era nuclear operations to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. This month, the Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total.

420

Mixed waste characterization reference document  

SciTech Connect (OSTI)

Waste characterization and monitoring are major activities in the management of waste from generation through storage and treatment to disposal. Adequate waste characterization is necessary to ensure safe storage, selection of appropriate and effective treatment, and adherence to disposal standards. For some wastes characterization objectives can be difficult and costly to achieve. The purpose of this document is to evaluate costs of characterizing one such waste type, mixed (hazardous and radioactive) waste. For the purpose of this document, waste characterization includes treatment system monitoring, where monitoring is a supplement or substitute for waste characterization. This document establishes a cost baseline for mixed waste characterization and treatment system monitoring requirements from which to evaluate alternatives. The cost baseline established as part of this work includes costs for a thermal treatment technology (i.e., a rotary kiln incinerator), a nonthermal treatment process (i.e., waste sorting, macronencapsulation, and catalytic wet oxidation), and no treatment (i.e., disposal of waste at the Waste Isolation Pilot Plant (WIPP)). The analysis of improvement over the baseline includes assessment of promising areas for technology development in front-end waste characterization, process equipment, off gas controls, and monitoring. Based on this assessment, an ideal characterization and monitoring configuration is described that minimizes costs and optimizes resources required for waste characterization.

NONE

1997-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

State waste discharge permit application, 200-E chemical drain field  

SciTech Connect (OSTI)

As part of the Hanford Federal Facility Agreement and Consent Order negotiations (Ecology et al. 1994), the US Department of Energy, Richland Operations Office, the US Environmental Protection Agency, and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground on the Hanford Site which affect groundwater or have the potential to affect ground would be subject to permitting under the structure of Chapter 173-216 (or 173-218 where applicable) of the Washington Administrative Code, the State Waste Discharge Permit Program. As a result of this decision, the Washington State Department of Ecology and the US Department of Energy, Richland Operations Office entered into Consent Order No. DE 91NM-177, (Ecology and DOE-RL 1991). The Consent Order No. DE 91NM-177 requires a series of permitting activities for liquid effluent discharges. This document presents the State Waste Discharge Permit (SWDP) application for the 200-E Chemical Drain Field. Waste water from the 272-E Building enters the process sewer line directly through a floor drain, while waste water from the 2703-E Building is collected in two floor drains, (north and south) that act as sumps and are discharged periodically. The 272-E and 2703-E Buildings constitute the only discharges to the process sewer line and the 200-E Chemical Drain Field.

Not Available

1994-06-01T23:59:59.000Z

422

Degradation of Dome Cutting Minerals in Hanford Waste - 13100  

SciTech Connect (OSTI)

At the Hanford Tank Farms, recent changes in retrieval technology require cutting new risers in several single-shell tanks. The Hanford Tank Farm Operator is using water jet technology with abrasive silicate minerals such as garnet or olivine to cut through the concrete and rebar dome. The abrasiveness of these minerals, which become part of the high-level waste stream, may enhance the erosion of waste processing equipment. However, garnet and olivine are not thermodynamically stable in Hanford waste, slowly degrading over time. How likely these materials are to dissolve completely in the waste before the waste is processed in the Waste Treatment and Immobilization Plant can be evaluated using theoretical analysis for olivine and collected direct experimental evidence for garnet. Based on an extensive literature study, a large number of primary silicates decompose into sodalite and cancrinite when exposed to Hanford waste. Given sufficient time, the sodalite also degrades into cancrinite. Even though cancrinite has not been directly added to any Hanford tanks during process times, it is the most common silicate observed in current Hanford waste. By analogy, olivine and garnet are expected to ultimately also decompose into cancrinite. Garnet used in a concrete cutting demonstration was immersed in a simulated supernate representing the estimated composition of the liquid retrieving waste from Hanford tank 241-C-107 at both ambient and elevated temperatures. This simulant was amended with extra NaOH to determine if adding caustic would help enhance the degradation rate of garnet. The results showed that the garnet degradation rate was highest at the highest NaOH concentration and temperature. At the end of 12 weeks, however, the garnet grains were mostly intact, even when immersed in 2 molar NaOH at 80 deg. C. Cancrinite was identified as the degradation product on the surface of the garnet grains. In the case of olivine, the rate of degradation in the high-pH regimes of a waste tank is expected to depend on two main parameters: carbonate is expected to slow olivine degradation rates, whereas hydroxide is expected to enhance olivine dissolution rates. Which of these two competing dissolution drivers will have a larger impact on the dissolution rate in the specific environment of a waste tank is currently not identifiable. In general, cancrinite is much smaller and less hard than either olivine or garnet, so would be expected to be less erosive to processing equipment. Complete degradation of either garnet or olivine prior to being processed at the Waste Treatment and Immobilization Plant cannot be confirmed, however. (authors)

Reynolds, Jacob G.; Cooke, Gary A.; Huber, Heinz J. [Washington River Protection Solutions, LLC, P.O. Box 850, Richland, WA 99352 (United States)] [Washington River Protection Solutions, LLC, P.O. Box 850, Richland, WA 99352 (United States)

2013-07-01T23:59:59.000Z

423

Degradation of dome cutting minerals in Hanford waste  

SciTech Connect (OSTI)

At the Hanford Tank Farms, recent changes in retrieval technology require cutting new risers in several single-shell tanks. The Hanford Tank Farm Operator is using water jet technology with abrasive silicate minerals such as garnet or olivine to cut through the concrete and rebar dome. The abrasiveness of these minerals, which become part of the high-level waste stream, may enhance the erosion of waste processing equipment. However, garnet and olivine are not thermodynamically stable in Hanford waste, slowly degrading over time. How likely these materials are to dissolve completely in the waste before the waste is processed in the Waste Treatment and Immobilization Plant can be evaluated using theoretical analysis for olivine and collected direct experimental evidence for garnet. Based on an extensive literature study, a large number of primary silicates decompose into sodalite and cancrinite when exposed to Hanford waste. Given sufficient time, the sodalite also degrades into cancrinite. Even though cancrinite has not been directly added to any Hanford tanks during process times, it is the most common silicate observed in current Hanford waste. By analogy, olivine and garnet are expected to ultimately also decompose into cancrinite. Garnet used in a concrete cutting demonstration was immersed in a simulated supernate representing the estimated composition of the liquid retrieving waste from Hanford tank 241-C-107 at both ambient and elevated temperatures. This simulant was amended with extra NaOH to determine if adding caustic would help enhance the degradation rate of garnet. The results showed that the garnet degradation rate was highest at the highest NaOH concentration and temperature. At the end of 12 weeks, however, the garnet grains were mostly intact, even when immersed in 2 molar NaOH at 80 deg C. Cancrinite was identified as the degradation product on the surface of the garnet grains. In the case of olivine, the rate of degradation in the high-pH regimes of a waste tank is expected to depend on two main parameters: carbonate is expected to slow olivine degradation rates, whereas hydroxide is expected to enhance olivine dissolution rates. Which of these two competing dissolution drivers will have a larger impact on the dissolution rate in the specific environment of a waste tank is currently not identifiable. In general, cancrinite is much smaller and less hard than either olivine or garnet, so would be expected to be less erosive to processing equipment. Complete degradation of either garnet or olivine prior to being processed at the Waste Treatment and Immobilization Plant cannot be confirmed, however.

Reynolds, Jacob G.; Huber, Heinz J.; Cooke, Gary A.

2013-01-11T23:59:59.000Z

424

Hazardous Waste/Mixed Waste Treatment Building throughput study  

SciTech Connect (OSTI)

The hazardous waste/mixed waste HW/MW Treatment Building (TB) is the specified treatment location for solid hazardous waste/mixed waste at SRS. This report provides throughput information on the facility based on known and projected waste generation rates. The HW/MW TB will have an annual waste input for the first four years of approximately 38,000 ft{sup 3} and have an annual treated waste output of approximately 50,000 ft{sup 3}. After the first four years of operation it will have an annual waste input of approximately 16,000 ft{sup 3} and an annual waste output of approximately 18,000 ft. There are several waste streams that cannot be accurately predicted (e.g. environmental restoration, decommissioning, and decontamination). The equipment and process area sizing for the initial four years should allow excess processing capability for these poorly defined waste streams. A treatment process description and process flow of the waste is included to aid in understanding the computations of the throughput. A description of the treated wastes is also included.

England, J.L.; Kanzleiter, J.P.

1991-12-18T23:59:59.000Z

425

Renewable Liquid Fuels Reforming  

Broader source: Energy.gov [DOE]

The Program anticipates that distributed reforming of biomass-derived liquid fuels could be commercial during the transition to hydrogen and used in the mid- and long-term time frames.

426

Glass former composition and method for immobilizing nuclear waste using the same  

DOE Patents [OSTI]

An alkoxide glass former composition has silica-containing constituents present as solid particulates of a particle size of 0.1 to 0.7 micrometers in diameter in a liquid carrier phase substantially free of dissolved silica. The glass former slurry is resistant to coagulation and may contain other glass former metal constituents. The immobilization of nuclear waste employs the described glass former by heating the same to reduce the volume, mixing the same with the waste, and melting the resultant mixture to encapsulate the waste in the resultant glass.

Cadoff, Laurence H. (Wilkins Township, Allegheny County, PA); Smith-Magowan, David B. (Washington, DC)

1988-01-01T23:59:59.000Z

427

Tank Waste Corporate Board Meeting 03/05/09 | Department of Energy  

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

3/05/09 3/05/09 Tank Waste Corporate Board Meeting 03/05/09 The following documents are associated with the Tank Waste Corporate Board Meeting held on March 5th, 2009. Overview of Integrated Waste Treatment Unit Desired PU Loading During Vitrification HLW System Integrated Project Team Waste Determination and Section 3116 of the 2005 National Defense Authorization Act - HQ Perspective Status of Art & Practice of Performance Assessment within the DOE Complex Experience from the Short Course on Introduction to Nuclear Chemistry and Fuel Cycle Separations and Future Educational Opportunities Role of Liquid Waste Pretreatment Technologies in Solving the DOE Clean-up Mission Performance Assessment Community of Practice Action Item Review and Status More Documents & Publications

428

INSTALLATION OF BUBBLERS IN THE SAVANNAH RIVER SITED DEFENSE WASTE PROCESSING FACILITY MELTER  

SciTech Connect (OSTI)

Savannah River Remediation (SRR) LLC assumed the liquid waste contract at the Savannah River Site (SRS) in the summer of 2009. The main contractual agreement was to close 22 High Level Waste (HLW) tanks in eight years. To achieve this aggressive commitment, faster waste processing throughout the SRS liquid waste facilities will be required. Part of the approach to achieve faster waste processing is to increase the canister production rate of the Defense Waste Processing Facility (DWPF) from approximately 200 canisters filled with radioactive waste glass per year to 400 canisters per year. To reach this rate for melter throughput, four bubblers were installed in the DWPF Melter in the late summer of 2010. This effort required collaboration between SRR, SRR critical subcontractor EnergySolutions, and Savannah River Nuclear Solutions, including the Savannah River National Laboratory (SRNL). The tasks included design and fabrication of the bubblers and related equipment, testing of the bubblers for various technical issues, the actual installation of the bubblers and related equipment, and the initial successful operation of the bubblers in the DWPF Melter.

Smith, M.; Iverson, D.

2010-12-08T23:59:59.000Z

429

Radionuclide Retention Mechanisms in Secondary Waste-Form Testing: Phase II  

SciTech Connect (OSTI)

This report describes the results from laboratory tests performed at Pacific Northwest National Laboratory (PNNL) for Washington River Protection Solutions (WRPS) to evaluate candidate stabilization technologies that have the potential to successfully treat liquid secondary waste stream effluents produced by the Hanford Tank Waste Treatment and Immobilization Plant (WTP). WRPS is considering the design and construction of a Solidification Treatment Unit (STU) for the Effluent Treatment Facility (ETF) at Hanford. The ETF, a multi-waste, treatment-and-storage unit that has been permitted under the Resource Conservation and Recovery Act (RCRA), can accept dangerous, low-level, and mixed wastewaters for treatment. The STU needs to be operational by 2018 to receive secondary liquid waste generated during operation of the WTP. The STU will provide the additional capacity needed for ETF to process the increased volume of secondary waste expected to be produced by WTP. This report on radionuclide retention mechanisms describes the testing and characterization results that improve understanding of radionuclide retention mechanisms, especially for pertechnetate, {sup 99}TcO{sub 4}{sup -} in four different waste forms: Cast Stone, DuraLith alkali aluminosilicate geopolymer, encapsulated fluidized bed steam reforming (FBSR) product, and Ceramicrete phosphate bonded ceramic. These data and results will be used to fill existing data gaps on the candidate technologies to support a decision-making process that will identify a subset of the candidate waste forms that are most promising and should undergo further performance testing.

Um, Wooyong; Valenta, Michelle M.; Chung, Chul-Woo; Yang, Jungseok; Engelhard, Mark H.; Serne, R. Jeffrey; Parker, Kent E.; Wang, Guohui; Cantrell, Kirk J.; Westsik, Joseph H.

2011-09-26T23:59:59.000Z

430

Waste generator services implementation plan  

SciTech Connect (OSTI)

Recurring waste management noncompliance problems have spurred a fundamental site-wide process revision to characterize and disposition wastes at the Idaho National Engineering and Environmental Laboratory. The reengineered method, termed Waste Generator Services, will streamline the waste acceptance process and provide waste generators comprehensive waste management services through a single, accountable organization to manage and disposition wastes in a timely, cost-effective, and compliant manner. This report outlines the strategy for implementing Waste Generator Services across the INEEL. It documents the culmination of efforts worked by the LMITCO Environmental Management Compliance Reengineering project team since October 1997. These efforts have included defining problems associated with the INEEL waste management process; identifying commercial best management practices; completing a review of DOE Complex-wide waste management training requirements; and involving others through an Integrated Process Team approach to provide recommendations on process flow, funding/charging mechanisms, and WGS organization. The report defines the work that will be performed by Waste Generator Services, the organization and resources, the waste acceptance process flow, the funding approach, methods for measuring performance, and the implementation schedule and approach. Field deployment will occur first at the Idaho Chemical Processing Plant in June 1998. Beginning in Fiscal Year 1999, Waste Generator Services will be deployed at the other major INEEL facilities in a phased approach, with implementation completed by March 1999.

Mousseau, J.; Magleby, M.; Litus, M.

1998-04-01T23:59:59.000Z

431

Method for co-processing waste rubber and carbonaceous material  

SciTech Connect (OSTI)

In a process for the co-processing of waste rubber and carbonaceous material to form a useful liquid product, the rubber and the carbonaceous material are combined and heated to the depolymerization temperature of the rubber in the presence of a source of hydrogen. The deploymerized rubber acts as a liquefying solvent for the carbonaceous material while a beneficial catalytic effect is obtained from the carbon black released on deploymerization the reinforced rubber. The reaction is carried out at liquefaction conditions of 380--600{degrees}C and 70--280 atmospheres hydrogen pressure. The resulting liquid is separated from residual solids and further processed such as by distillation or solvent extraction to provide a carbonaceous liquid useful for fuels and other purposes.

Farcasiu, M.; Smith, C.M.

1990-10-09T23:59:59.000Z

432

Transuranic Waste Tabletop  

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

Transuranic (TRU) Waste Transuranic (TRU) Waste (Hazard Class 7 Radioactive) Moderator's Version of Tabletop Prepared for the Department of Energy Office of Transportation and Emergency Management 02B00215-07D.p65 This page intentionally left blank table of contents Transportation Emergency Preparedness Program (TEPP) planning tools planning tools planning tools planning tools T T T T Tr r r r ransur ansur ansur ansur ansuranic (TRU) W anic (TRU) W anic (TRU) W anic (TRU) W anic (TRU) Waste aste aste aste aste (Hazar (Hazar (Hazar (Hazar (Hazard Class 7 Radio d Class 7 Radio d Class 7 Radio d Class 7 Radio d Class 7 Radioactiv activ activ activ active) e) e) e) e) Moder Moder Moder Moder Moderat at at at ator' or' or' or' or's V s V s V s V s Version of T ersion of T ersion of T ersion of T ersion of Tablet ablet ablet ablet abletop

433

Pioneering Nuclear Waste Disposal  

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

2 2 3 T he journey to the WIPP began nearly 60 years before the first barrels of transuranic waste arrived at the repository. The United States produced the world's first sig- nificant quantities of transuranic material during the Manhattan Project of World War II in the early 1940s. The government idled its plutonium- producing reactors and warhead manu- facturing plants at the end of the Cold War and scheduled most of them for dismantlement. However, the DOE will generate more transuranic waste as it cleans up these former nuclear weapons facilities. The WIPP is a cor- nerstone of the effort to clean up these facilities by providing a safe repository to isolate transuranic waste in disposal rooms mined out of ancient salt beds, located 2,150 feet below ground. The need for the WIPP

434

FROM WASTE TO WORTH: THE ROLE OF WASTE DIVERSION IN  

E-Print Network [OSTI]

;Canadian Energy-From-Waste Coalition (CEFWC) 1 There is considerable merit to the ideas outlined commitment to foster a green and sustainable economy. The Canadian Energy-From-Waste Coalition (CEFWC sign that the system is failing. #12;Canadian Energy-From-Waste Coalition (CEFWC) 2 Like you, the CEFWC

Columbia University

435

Waste IncIneratIon and Waste PreventIon  

E-Print Network [OSTI]

disposing of waste, it also makes consider- able amounts of energy available in the form of electricity emissions annu- ally. About 50 percent of the energy contained in residual municipal waste comes from- sions from the fossil waste fraction and the fos- sil energy purchased from external sources

436

Waste Management Plan for the Remedial Investigation of Waste Area Grouping 10, Operable Unit 3, at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program  

SciTech Connect (OSTI)

This Waste Management Plan (WMP) supplements the Remedial Investigation/Feasibility Study (RI/FS) Project WMP and defines the criteria and methods to be used for managing and characterizing waste generated during activities associated with the RI of 23 wells near the Old Hydrofracture Facility (OHF). These wells are within the Waste Area Grouping (WAG) 5 area of contamination (AOC) at Oak Ridge National Laboratory (ORNL). Field activities for the limited RI of Operable Unit (OU) 3 of WAG 10 will involve sampling and measurement of various environmental media (e.g., liquids and gases). Many of these activities will occur in areas known to be contaminated with radioactive materials or hazardous chemical substances, and it is anticipated that contaminated solid and liquid wastes and noncontaminated wastes will be generated as a result of these activities. On a project-wide basis, handling of these waste materials will be accomplished in accordance with the RI/FS Project WMP and the procedures referenced throughout the plan.

Not Available

1993-10-01T23:59:59.000Z

437

Ion Recognition Approach to Volume Reduction of Alkaline Tank Waste by Separation and Recycle of Sodium Hydroxide and Sodium Nitrate  

SciTech Connect (OSTI)

This research has focused on new liquid-liquid extraction chemistry applicable to separation of major sodium salts from alkaline tank waste. It was the overall goal to provide the scientific foundation upon which the feasibility of liquid-liquid extraction chemistry for bulk reduction of the volume of tank waste can be evaluated. Sodium hydroxide represented the initial test case and primary focus. It is a primary component of the waste1 and has the most value for recycle. A full explanation of the relevance of this research to USDOE Environmental Management needs will be given in the Relevance, Impact, and Technology Transfer section below. It should be noted that this effort was predicated on the need for sodium removal primarily from low-activity waste, whereas evolving needs have shifted attention to volume reduction of the high-activity waste. The results of the research to date apply to both applications, though treatment of high-activity wastes raises new questions that will be addressed in the renewal period. Toward understanding the extractive chemistry of sodium hydroxide and other sodium salts, it was the intent to identify candidate extractants and determine their applicable basic properties regarding selectivity, efficiency, speciation, and structure. A hierarchical strategy was to be employed in which the type of liquid-liquid-extraction system varied in sophistication from simple, single-component solvents to solvents containing designer host molecules. As an aid in directing this investigation toward addressing the fundamental questions having the most value, a conceptualization of an ideal process was advanced. Accordingly, achieving adequate selectivity for sodium hydroxide represented a primary goal, but this result is worthwhile for waste applications only if certain conditions are met.

Moyer, Bruce A.; Marchand, Alan P.; Bonnesen, Peter V.; Bryan, Jeffrey C.; Haverlock, Tamara J.

2002-03-30T23:59:59.000Z

438

Skutterudite Thermoelectric Generator For Automotive Waste Heat...  

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

Skutterudite Thermoelectric Generator For Automotive Waste Heat Recovery Skutterudite Thermoelectric Generator For Automotive Waste Heat Recovery Skutterudite TE modules were...

439

Waste Heat Recovery Opportunities for Thermoelectric Generators...  

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

Waste Heat Recovery Opportunities for Thermoelectric Generators Waste Heat Recovery Opportunities for Thermoelectric Generators Thermoelectrics have unique advantages for...

440

High-Level Waste Requirements  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The guide provides the criteria for determining which DOE radioactive wastes are to be managed as high-level waste in accordance with DOE M 435.1-1.

1999-07-09T23:59:59.000Z

Note: This page contains sample records for the topic "liquid waste lw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Pathology waste includes: Transgenic animals.  

E-Print Network [OSTI]

resistant, have tight fitting covers, be clean, and in good repair. · Pathology waste must be transferred via the Internet: · Visit www.ehs.uci.edu/programs/enviro/. · Fill out the "Biomedical Waste

George, Steven C.

442

Waste Management Coordinating Lead Authors  

E-Print Network [OSTI]

-use and recycling ..............602 10.4.6 Wastewater and sludge treatment.....................602 10.4.7 Waste ............................................591 10.2.2 Wastewater generation ....................................592 10.2.3 Development trends for waste and ......................... wastewater ......................................................593

Columbia University

443

Leaching of Nuclear Waste Glasses  

Science Journals Connector (OSTI)

Resistance to aqueous corrosion is the most important requirement of glasses designed to immobilize high level radioactive wastes. Obtaining a highly durable nuclear waste glass is complicated by the requirement ...

L. L. Hench

1985-01-01T23:59:59.000Z

444

The Discovery of Nuclear Waste  

Science Journals Connector (OSTI)

When did man discover nuclear waste? To answer this question, we first have to ask if nuclear waste really is something that could be called ... Prize in physics. In early writings within nuclear energy research ...

Gran Sundqvist

2002-01-01T23:59:59.000Z

445

Nuclear Waste Disposal Plan Drafted  

Science Journals Connector (OSTI)

Nuclear Waste Disposal Plan Drafted ... Of all the issues haunting nuclear power plants, that of disposing of the radioactive wastes and spent nuclear fuel they generate has been the most vexing. ...

1984-01-09T23:59:59.000Z

446

Hydrothermal Processing of Wet Wastes  

Broader source: Energy.gov [DOE]

Breakout Session 3AConversion Technologies III: Energy from Our WasteWill we Be Rich in Fuel or Knee Deep in Trash by 2025? Hydrothermal Processing of Wet Wastes James R. Oyler, President, Genifuel Corporation

447

Zero Waste, Renewable Energy & Environmental  

E-Print Network [OSTI]

· Dioxins & Furans · The `State of Waste' in the US · WTE Technologies · Thermal Recycling ­ Turnkey dangerous wastes in the form of gases and ash, often creating entirely new hazards, like dioxins and furans

Columbia University

448

Delaware Solid Waste Authority (Delaware)  

Broader source: Energy.gov [DOE]

The Delaware Solid Waste Authority (DSWA) runs three landfills, all of which recover methane and generate electricity with a total capacity of 24 MWs. The DSWA Solid Waste Plan includes goals,...

449

Explosive Waste Treatment Facility  

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

106 106 Environment a 1 Assessment for th.e Explosive Waste Treatment Facility at Site 300 Lawrence Livermore National Laboratory MASTER November 1995 U.S. Department of Energy Office of Environmental Restoration and Waste Management Washington, DOC. 20585 Portions of this document maly be illegible in electronic image products. Images are produced from the best available original document. Table of Contents 1 . 0 2.0 3 . 0 4.0 5 . 0 6.0 7 . 0 8 . 0 Document Summary .............................................................. 1 Purpose and Need for Agency Action ............................................. 3 Description of the Proposed Action and Alternatives ............................ 4 3.1.1 Location ............................................................. 4

450

Waste Isolation Pilot Plant  

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

Waste Isolation Pilot Plant Waste Isolation Pilot Plant AFFIDAVIT FOR SURVIVING RELATIVE STATE _______________ ) ) ss: __________________ COUNTY OF _____________ ) That I, ________________________, am the _________________________ (Indicate relationship) of ___________________________, who is deceased and make the attached request pursuant to 10 CFR, Section 1008. That the information contained on the attached request is true and correct to the best of my knowledge and belief, and I am signing this authorization subject to the penalties provided in 18 U.S.C. 1001. ____________________________ SIGNATURE NOTARIZATION: SUBSCRIBED and SWORN to before me this ______day of __________, 20_____

451

Converter waste disposal study  

SciTech Connect (OSTI)

The importance of waste management and disposal issues to the converting and print industries is demonstrated by the high response rate to a survey of US and Canadian converters and printers. The 30-item questionnaire measured the impact of reuse, recycling, source reduction, incineration, and landfilling on incoming raw-material packaging, process scrap, and waste inks, coatings, and adhesives. The results indicate that significant amounts of incoming packaging materials are reused in-house or through supplier take-back programs. However, there is very little reuse of excess raw materials and process scrap, suggesting the need for greater source reduction within these facilities as the regulatory climate becomes increasingly restrictive.

Schultz, R.B. (RBS Technologies, Inc., Skokie, IL (United States))

1993-07-01T23:59:59.000Z

452

Frostbite Theater - Liquid Nitrogen Experiments - Dry Ice vs. Liquid  

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

Egg + Liquid Nitrogen + Time-lapse! Egg + Liquid Nitrogen + Time-lapse! Previous Video (Egg + Liquid Nitrogen + Time-lapse!) Frostbite Theater Main Index Next Video (Liquid Nitrogen Cooled Dry Ice in Water!) Liquid Nitrogen Cooled Dry Ice in Water! Dry Ice vs. Liquid Nitrogen! Dry ice is cold. Liquid nitrogen is cold, too. What happens when the two are mixed together? [ Show Transcript ] Announcer: Frostbite Theater presents... Cold Cuts! No baloney! Joanna and Steve: Just science! Joanna: Hi! I'm Joanna! Steve: And I'm Steve! Joanna: Have you ever wondered what happens when you mix dry ice and liquid nitrogen? Steve: Well, we just happen to have a chunk of dry ice left over from when we filmed 'How to Make a Cloud Chamber,' and here at Jefferson Lab, liquid nitrogen flows like water, so we're going to find out!

453

DOE/EIS-0287 Idaho High-Level Waste & Facilities Disposition Draft Environmental Impact Statement (December 1999)  

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

HLW & FD EIS HLW & FD EIS 3-13 DOE/EIS-0287D Calcine storag e i n b i n s ets Calcine storag e i n b i n s et s Cesium ion exchange & grouting Cesium ion exchange & grouting NWCF* NWCF* Calcine Mixed transuranic waste/SBW Mixed transuranic waste/NGLW Low-level waste disposa l*** disposa l*** Tank heels Transuranic waste (from tank heels) * * * * Mixed transuranic waste/ NGLW Mixed transuranic waste/ NGLW M i x e d t r a nsuran ic w a s t e / M i x e d t r a nsuran ic w a s t e / S B W s t o rage in Ta n k F a r m S B W s t o rage in Ta n k F a r m Low-leve l waste Low-leve l waste FIGURE 3-2. Continued Current Operations Alternative. LEGEND * Including high-temperature and maximum achievable control technology upgrades. Mixed transuranic waste/ newly generated liquid waste New Waste Calcining Facility ** Calcine would be transferred from bin set #1 to bin set #6 or #7.

454

Ion Recognition Approach to Volume Reduction of Alkaline Tank Waste by Separation and Recycle of Sodium Hydroxide and Sodium Nitrate  

SciTech Connect (OSTI)

Disposal of high-level nuclear waste is horrendously expensive, in large part because the actual radioactive matter in the tanks has been diluted over 1000-fold by ordinary inorganic chemicals. Treatment processes themselves can exacerbate the problem by adding further volume to the waste. Waste retrieval and sludge washing, for example, will require copious amounts of sodium hydroxide. If the needed sodium hydroxide could be separated from the waste and recycled, however, the addition of fresh sodium hydroxide could be avoided, ultimately reducing the final waste volume and associated disposal costs. The major objective of this research is to explore new liquid-liquid extraction approaches to the selective separation of sodium hydroxide from alkaline high-level wastes stored in underground tanks at the Hanford and Savannah River sites. Consideration is also given to separating potassium and abundant anions, including nitrate, nitrite, aluminate, and carbonate. Salts of these ions represent possible additional value for recycle, alternative disposal, or even use as commodity chemicals. A comprehensive approach toward understanding the extractive chemistry of these salts is envisioned, involving systems of varying complexity, from use of simple solvents to new bifunctional host molecules for ion-pair recognition. These extractants will ideally require no adjustment of the waste composition and will release the extracted salt into water, thereby consuming no additional chemicals and producing no additional waste volume. The overall goal of this research is to provide a scientific foundation upon which the feasibility of new liquid-liquid extraction chemistry applicable to the bulk reduction of the volume of tank waste can be evaluated.

Moyer, Bruce A.; Marchand, Alan P.

2001-06-01T23:59:59.000Z

455

Ion Recognition Approach to Volume Reduction of Alkaline Tank Waste by Separation and Recycle of Sodium Hydroxide and Sodium Nitrate  

SciTech Connect (OSTI)

The objective of this research is to explore new liquid-liquid extraction approaches to the selective separation of major sodium salts from alkaline high-level wastes stored in underground tanks at Hanford, Savannah River, and Oak Ridge sites. Disposal of high level waste is horrendously expensive, in large part because the actual radioactive matter in the tanks has been diluted over 1000-fold by ordinary inorganic chemicals. Since the residual bulk chemicals must still undergo expensive treatment and disposal after most of the hazardous radionuclides have been removed, large cost savings will result from processes that reduce the overall waste volume. It is proposed that major cost savings can be expected if sodium hydroxide needed for sludge washing can be obtained from the waste itself, thus avoiding the addition of yet another bulk chemical to the waste and still further increase of the waste volume and disposal cost. Secondary priority is given to separating potassium an d abundant anions, including nitrate, nitrite, aluminate, and carbonate. Salts of these ions represent possible additional value for recycle, alternative disposal, or even use as commodity chemicals. A comprehensive approach toward understanding the extractive chemistry of these salts is envisioned, involving systems of varying complexity, from use of simple solvents to new bifunctional host molecules for ion-pair recognition. These extractants will ideally require no adjustment of the waste composition and will release the extracted salt into water, thereby consuming no additional chemicals and producing no additional waste volume. The overall goal of this research is to provide a scientific foundation upon which the feasibility of new liquid-liquid extraction chemistry applicable to the bulk reduction of the volume of tank waste can be evaluated.

Moyer, Bruce A.; Marchand, Alan P.; Bryan, Jeffrey C.; Bonnesen, Peter V.

1999-06-01T23:59:59.000Z

456

Ion Recognition Approach to Volume Reduction of Alkaline Tank Waste by Separation and Recycle of Sodium Hydroxide and Sodium Nitrate  

SciTech Connect (OSTI)

Disposal of high- level waste is horrendously expensive, in large part because the actual radioactive matter in the tanks has been diluted over 1000-fold by ordinary inorganic chemicals. Treatment processes themselves can exacerbate the problem by adding further volume to the waste. Waste retrieval and sludge washing, for example, will require copious amounts of sodium hydroxide. If the needed sodium hydroxide could be separated from the waste and recycled, however, the addition of fresh sodium hydroxide could be avoided, ultimately reducing the final waste volume and associated disposal costs. The major objective of this research is to explore new liquid- liquid extraction approaches to the selective separation of sodium hydroxide from alkaline high-level wastes stored in underground tanks at the Hanford and Savannah River sites. Consideration is also given to separating potassium and abundant anions, including nitrate, nitrite, aluminate, and carbonate. Salts of these ions represent possible additional value for recycle, alternative disposal, or even use as commodity chemicals. A comprehensive approach toward understanding the extractive chemistry of these salts is envisioned, involving systems of varying complexity, from use of simple solvents to new bifunctional host molecules for ion-pair recognition. These extractants will ideally require no adjustment of the waste composition and will release the extracted salt into water, thereby consuming no additional chemicals and producing no additional waste volume. The overall goal of this research is to provide a scientific foundation upon which the feasibility of new liquid-liquid extraction chemistry applicable to the bulk reduction of the volume of tank waste can be evaluated.

Moyer, Bruce A.; Marchand, Alan P.

2000-06-01T23:59:59.000Z

457

WORLDWIDE FOCUS ON NUCLEAR WASTE  

Science Journals Connector (OSTI)

WORLDWIDE FOCUS ON NUCLEAR WASTE ... Volume grows and years pile up, but world lacks consensus on disposing of nuclear waste ... WHAT TO DO WITH SPENT nuclear fuel and high-level radioactive waste is a problem shared by much of the world. ...

JEFF JOHNSON

2001-06-18T23:59:59.000Z

458

RETHINKING WASTE, RECYCLING, AND HOUSEKEEPING  

E-Print Network [OSTI]

RETHINKING WASTE, RECYCLING, AND HOUSEKEEPING EFFICIENCY.EFFICIENCY. A l GA leaner Green #12 t R li Management Recycling Staff The Office of Waste Reduction & Recycling started in The Office of Waste Reduction & Recycling started in 1990, we have 14 full time staff positions. ·We collect over 40

Howitt, Ivan

459

Mixed Waste Working Group report  

SciTech Connect (OSTI)

The treatment of mixed waste remains one of this country`s most vexing environmental problems. Mixed waste is the combination of radioactive waste and hazardous waste, as defined by the Resource Conservation and Recovery Act (RCRA). The Department of Energy (DOE), as the country`s largest mixed waste generator, responsible for 95 percent of the Nation`s mixed waste volume, is now required to address a strict set of milestones under the Federal Facility Compliance Act of 1992. DOE`s earlier failure to adequately address the storage and treatment issues associated with mixed waste has led to a significant backlog of temporarily stored waste, significant quantities of buried waste, limited permanent disposal options, and inadequate treatment solutions. Between May and November of 1993, the Mixed Waste Working Group brought together stakeholders from around the Nation. Scientists, citizens, entrepreneurs, and bureaucrats convened in a series of forums to chart a course for accelerated testing of innovative mixed wa