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1

Temperature programmed combustion studies of the co-processing of coal and waste materials  

E-Print Network (OSTI)

Temperature programmed combustion studies of the co-processing of coal and waste materials F) to study the interaction between coal, polyethylene, and dried sewage sludge which are possible components in coal/ waste materials co-processing combustion systems. The TPC studies were carried out on the raw

Thomas, Mark

2

Idaho Chemical Processing Plant spent fuel and waste management technology development program plan: 1994 Update  

SciTech Connect

The Department of Energy has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage since 1951 and reprocessing since 1953. Until April 1992, the major activity of the ICPP was the reprocessing of SNF to recover fissile uranium and the management of the resulting high-level wastes (HLW). In 1992, DOE chose to discontinue reprocessing SNF for uranium recovery and shifted its focus toward the continued safe management and disposition of SNF and radioactive wastes accumulated through reprocessing activities. Currently, 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste), 3,800 cubic meters of calcine waste, and 289 metric tons heavy metal of SNF are in inventory at the ICPP. Disposal of SNF and high-level waste (HLW) is planned for a repository. Preparation of SNF, HLW, and other radioactive wastes for disposal may include mechanical, physical, and/or chemical processes. This plan outlines the program strategy of the ICPP spent Fuel and Waste Management Technology Development Program (SF&WMTDP) to develop and demonstrate the technology required to ensure that SNF and radioactive waste will be properly stored and prepared for final disposal in accordance with regulatory drivers. This Plan presents a brief summary of each of the major elements of the SF&WMTDP; identifies key program assumptions and their bases; and outlines the key activities and decisions that must be completed to identify, develop, demonstrate, and implement a process(es) that will properly prepare the SNF and radioactive wastes stored at the ICPP for safe and efficient interim storage and final disposal.

1994-09-01T23:59:59.000Z

3

Idaho Chemical Processing Plant low-activity waste grout stabilization development program FY-97 status report  

SciTech Connect

The general purpose of the Grout Development Program is to solidify and stabilize the liquid low-activity wastes (LAW) generated at the Idaho Chemical Processing Plant (ICPP). It is anticipated that LAW will be produced from the following: (1) chemical separation of the tank farm high-activity sodium-bearing waste, (2) retrieval, dissolution, and chemical separation of the aluminum, zirconium, and sodium calcines, (3) facility decontamination processes, and (4) process equipment waste. Grout formulation studies for sodium-bearing LAW, including decontamination and process equipment waste, continued this fiscal year. A second task was to develop a grout formulation to solidify potential process residual heels in the tank farm vessels when the vessels are closed.

Herbst, A.K.; Marshall, D.W.; McCray, J.A.

1998-02-01T23:59:59.000Z

4

Nuclear Safety R&D in the Waste Processing Technology Development & Deployment Program  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

R&D in the Waste Processing R&D in the Waste Processing Technology Development & Deployment Program Presentation to the DOE High Level Waste Corporate Board July 29, 2009 Al Baione Office of Waste Processing DOE-EM Office of Engineering & Technology 2 Outline Nuclear Safety Research & Development Overview Summary of EM- NSR&D Presentations from February 2009 Evaluating Performance of Nuclear Grade HEPA Filters under Fire/Smoke Challenge Conditions Structural Integrity Initiative for HLW Tanks Pipeline Plugging and Prevention Advanced Mixing Models Basic Science Opportunities in HLW Storage and Processing Safety Cementitious Barriers Partnership 3 Nuclear Safety Research & Development Overview DNFSB 2004-1 identified need for renewed DOE attention to nuclear safety R&D

5

Idaho Chemical Processing Plant low-level waste grout stabilization development program FY-96 status report  

Science Conference Proceedings (OSTI)

The general purpose of the Grout Stabilization Development Program is to solidify and stabilize the liquid low-level wastes (LLW) generated at the Idaho Chemical Processing Plant (ICPP). It is anticipated that LLW will be produced from the following: (1) chemical separation of the tank farm high-activity sodium-bearing waste; (2) retrieval, dissolution, and chemical separation of the aluminum, zirconium, and sodium calcines; (3) facility decontamination processes; and (4) process equipment waste. The main tasks completed this fiscal year as part of the program were chromium stabilization study for sodium-bearing waste and stabilization and solidification of LLW from aluminum and zirconium calcines. The projected LLW will be highly acidic and contain high amounts of nitrates. Both of these are detrimental to Portland cement chemistry; thus, methods to precondition the LLW and to cure the grout were explored. A thermal calcination process, called denitration, was developed to solidify the waste and destroy the nitrates. A three-way blend of Portland cement, blast furnace slag, and fly ash was successfully tested. Grout cubes were prepared at various waste loadings to maximize loading while meeting compressive strength and leach resistance requirements. For the sodium LLW, a 25% waste loading achieves a volume reduction of 3.5 and a compressive strength of 2,500 pounds per square inch while meeting leach, mix, and flow requirements. It was found that the sulfur in the slag reduces the chromium leach rate below regulatory limits. For the aluminum LLW, a 15% waste loading achieves a volume reduction of 8.5 and a compressive strength of 4,350 pounds per square inch while meeting leach requirements. Likewise for zirconium LLW, a 30% waste loading achieves a volume reduction of 8.3 and a compressive strength of 3,570 pounds per square inch.

Herbst, A.K.

1996-09-01T23:59:59.000Z

6

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-2000 Status Report  

SciTech Connect

The Low-Activity Waste Process Technology Program anticipated that grouting will be used for disposal of low-level and transuranic wastes generated at the Idaho Nuclear Technology Engineering Center (INTEC). During fiscal year 2000, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed using silica gel and other absorbents to solidify sodium-bearing wastes. A feasibility study and conceptual design were completed for the construction of a grout pilot plant for simulated wastes and demonstration facility for actual wastes.

Herbst, A.K.; McCray, J.A.; Kirkham, R.J.; Pao, J.; Argyle, M.D.; Lauerhass, L.; Bendixsen, C.L.; Hinckley, S.H.

2000-10-31T23:59:59.000Z

7

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-2000 Status Report  

SciTech Connect

The Low-Activity Waste Process Technology Program anticipated that grouting will be used for disposal of low-level and transuranic wastes generated at the Idaho Nuclear Technology Engineering Center (INTEC). During fiscal year 2000, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed using silica gel and other absorbents to solidify sodium-bearing wastes. A feasibility study and conceptual design were completed for the construction of a grout pilot plant for simulated wastes and demonstration facility for actual wastes.

Herbst, Alan Keith; Mc Cray, John Alan; Kirkham, Robert John; Pao, Jenn Hai; Argyle, Mark Don; Lauerhass, Lance; Bendixsen, Carl Lee; Hinckley, Steve Harold

2000-11-01T23:59:59.000Z

8

Use of the Environmental Simulation Program (ESP) to Simulate Complex Waste Treatment Processes  

Science Conference Proceedings (OSTI)

The Environmental Simulation Program is a process simulator designed for aqueous based chemical processes. ESP, which is produced by OLI Systems, Inc., utilizes sophisticated activity coefficient models and predictive equations that result in the ability to simulate very complex electrolyte systems (OLI, 2002). The software comes with databanks of regressed parameters for a large number of aqueous, vapor, and solid species covering most of the elements. ESP has been used extensively at the U. S. Department of Energy Hanford Site to predict nuclear waste slurry vapor-liquid-solid equilibrium. It has and is being used to model leaching and washing of nuclear waste sludges, evaporation of nuclear waste solutions, crystallization of salts, precipitation of plutonium and other metals from waste solutions, and other processing of dilute and concentrated aqueous solutions, sludges, and slurries. The software is also used extensively to rationalize the characterization of nuclear wastes using limited data from analyses of waste samples. The OLI provided databanks suffer from a legacy interaction model that limits the accuracy when neutral solutes are important. Also, the nitrate-nitrite systems typically found in nuclear wastes are not properly parameterized in ESP databases because of the existence of sodium nitrate and nitrite ion pairs. Properties databanks for ESP have been developed at Flour Federal Services that eliminate the legacy model and provide more accurate simulation results than the OLI supplied databases for such concentrated solutions and slurries.

MacLean, G. T.; Ho, Q. T.; Berger, S. R. K.

2003-02-26T23:59:59.000Z

9

Idaho Chemical Processing Plant Spent Fuel and Waste Management Technology Development Program Plan  

SciTech Connect

The Department of Energy (DOE) has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage and reprocessing since 1953. Reprocessing of SNF has resulted in an existing inventory of 1.5 million gallons of radioactive sodium-bearing liquid waste and 3800 cubic meters (m{sup 3}) of calcine, in addition to the 768 metric tons (MT) of SNF and various other fuel materials in inventory. To date, the major activity of the ICPP has been the reprocessing of SNF to recover fissile uranium; however, recent changes in world events have diminished the demand to recover and recycle this material. As a result, DOE has discontinued reprocessing SNF for uranium recovery, making the need to properly manage and dispose of these and future materials a high priority. In accordance with the Nuclear Waste Policy Act (NWPA) of 1982, as amended, disposal of SNF and high-level waste (HLW) is planned for a geological repository. Preparation of SNF, HLW, and other radioactive wastes for disposal may include mechanical, physical, and/or chemical processes. This plan outlines the program strategy of the ICPP Spent Fuel and Waste Management Technology Development Program (SF&WMTDP) to develop and demonstrate the technology required to ensure that SNF and radioactive waste will properly stored and prepared for final disposal. Program elements in support of acceptable interim storage and waste minimization include: developing and implementing improved radioactive waste treatment technologies; identifying and implementing enhanced decontamination and decommissioning techniques; developing radioactive scrap metal (RSM) recycle capabilities; and developing and implementing improved technologies for the interim storage of SNF.

1993-09-01T23:59:59.000Z

10

Technology development program for Idaho Chemical Processing Plant spent fuel and waste management  

SciTech Connect

Acidic high-level radioactive waste (HLW) resulting from fuel reprocessing at the Idaho Chemical Processing Plant (ICPP) for the U.S. Department of Energy (DOE) has been solidified to a calcine since 1963 and stored in stainless steel bins enclosed by concrete vaults. Several different types of unprocessed irradiated DOE-owned fuels are also in storage at the ICPP. In April, 1992, DOE announced that spent fuel would no longer be reprocessed to recover enriched uranium and called for a shutdown of the reprocessing facilities at the ICPP. A new Spent Fuel and HLW Technology Development program was subsequently initiated to develop technologies for immobilizing ICPP spent fuels and HLW for disposal, in accordance with the Nuclear Waste Policy Act. The Program elements include Systems Analysis, Graphite Fuel Disposal, Other Spent Fuel Disposal, Sodium-Bearing Liquid Waste Processing, Calcine Immobilization, and Metal Recycle/Waste Minimization. This paper presents an overview of the ICPP radioactive wastes and current spent fuels, and describes the Spent Fuel and HLW Technology program in more detail.

Ermold, L.F.; Knecht, D.A.; Hogg, G.W.; Olson, A.L.

1993-08-01T23:59:59.000Z

11

SRS - Programs - Waste Solidification  

NLE Websites -- All DOE Office Websites (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

12

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-99 Status Report  

SciTech Connect

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1999, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed on radionuclide leaching, microbial degradation, waste neutralization, and a small mockup for grouting the INTEC underground storage tank residual heels.

Herbst, Alan Keith; Mc Cray, John Alan; Kirkham, Robert John; Pao, Jenn Hai; Hinckley, Steve Harold

1999-10-01T23:59:59.000Z

13

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-99 Status Report  

SciTech Connect

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1999, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed on radionuclide leaching, microbial degradation, waste neutralization, and a small mockup for grouting the INTEC underground storage tank residual heels.

A. K. Herbst; J. A. McCray; R. J. Kirkham; J. Pao; S. H. Hinckley

1999-09-30T23:59:59.000Z

14

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-98 Status Report  

SciTech Connect

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels.

Herbst, Alan Keith; Mc Cray, John Alan; Rogers, Adam Zachary; Simmons, R. F.; Palethorpe, S. J.

1999-03-01T23:59:59.000Z

15

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program, FY-98 Status Report  

SciTech Connect

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels.

Herbst, A.K.; Rogers, A.Z.; McCray, J.A.; Simmons, R.F.; Palethorpe, S.J.

1999-03-01T23:59:59.000Z

16

Hanford Waste Vitrification Plant Project Waste Form Qualification Program Plan  

SciTech Connect

The US Department of Energy has created a waste acceptance process to help guide the overall program for the disposal of high-level nuclear waste in a federal repository. This Waste Form Qualification Program Plan describes the hierarchy of strategies used by the Hanford Waste Vitrification Plant Project to satisfy the waste form qualification obligations of that waste acceptance process. A description of the functional relationship of the participants contributing to completing this objective is provided. The major activities, products, providers, and associated scheduling for implementing the strategies also are presented.

Randklev, E.H.

1993-06-01T23:59:59.000Z

17

SRS - Programs - Liquid Waste Disposition  

NLE Websites -- All DOE Office Websites (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.

18

Waste Management Process Improvement Project  

SciTech Connect

The Bechtel Hanford-led Environmental Restoration Contractor team's Waste Management Process Improvement Project is working diligently with the U.S. Department of Energy's (DOE) Richland Operations Office to improve the waste management process to meet DOE's need for an efficient, cost-effective program for the management of dangerous, low-level and mixed-low-level waste. Additionally the program must meet all applicable regulatory requirements. The need for improvement was highlighted when a change in the Groundwater/Vadose Zone Integration Project's waste management practices resulted in a larger amount of waste being generated than the waste management organization had been set up to handle.

Atwood, J.; Borden, G.; Rangel, G. R.

2002-02-25T23:59:59.000Z

19

Citrus Waste Biomass Program  

DOE Green Energy (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

20

Tank Farm Waste Transfer Compatibility Program  

SciTech Connect

The compatibility program described in this document formalizes the process for determining waste compatibility. The primary goal of the program is to ensure that sufficient controls are in place to prevent the formation of incompatible mixtures during future operations. The process described involves characterizing waste, comparing characteristics with criteria, resolving potential incompatibilities and documenting the process.

FOWLER, K.D.

2000-07-12T23:59:59.000Z

Note: This page contains sample records for the topic "waste processing program" 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

Technology development program for Idaho Chemical Processing Plant spent fuel and waste management  

SciTech Connect

Irradiated nuclear fuel has been reprocessed at the Idaho Chemical Processing Plant (ICPP) since 1953 to recover uranium-235 and krypton-85 for the US Department of Energy (DOE). The resulting acidic high-level liquid radioactive waste (HLLW) has been solidified to a high-level waste (HLW) calcine since 1963 and stored in stainless-steel bins enclosed in concrete vaults. Residual HLW and radioactive sodium-bearing waste are stored in stainless-steel underground tanks contained in concrete vaults. Several different types of unprocessed irradiated DOE-owned fuels are also stored at INEL. In April, 1992, DOE announced that spent fuel would no longer be reprocessed to recover enriched uranium. As a result of the decision to curtail reprocessing the ICPP Spent Fuel and Waste Management Technology Development plan has been implemented to identify acceptable options for disposing of the (1) sodium-bearing liquid radioactive waste, (2) radioactive calcine, and (3) irradiated spent fuel stored at the INEL. The plan was developed jointly by DOE and Westinghouse Idaho Nuclear Company, Inc., (WINCO) and with the concurrence of the State of Idaho.

Ermold, L.F.; Knecht, D.A.; Hogg, G.W.; Olson, A.L.

1993-06-01T23:59:59.000Z

22

Municipal waste processing apparatus  

DOE Patents (OSTI)

This invention relates to apparatus for processing municipal waste, and more particularly to vibrating mesh screen conveyor systems for removing grit, glass, and other noncombustible materials from dry municipal waste. Municipal waste must be properly processed and disposed of so that it does not create health risks to the community. Generally, municipal waste, which may be collected in garbage trucks, dumpsters, or the like, is deposited in processing areas such as landfills. Land and environmental controls imposed on landfill operators by governmental bodies have increased in recent years, however, making landfill disposal of solid waste materials more expensive. 6 figs.

Mayberry, J.L.

1988-04-13T23:59:59.000Z

23

Hazardous Waste Program (Alabama)  

Energy.gov (U.S. Department of Energy (DOE))

This rule states criteria for identifying the characteristics of hazardous waste and for listing hazardous waste, lists of hazardous wastes, standards for the management of hazardous waste and...

24

Salt Waste Processing Initiatives  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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%)

25

Solid Waste Management Program (Missouri)  

Energy.gov (U.S. Department of Energy (DOE))

The Solid Waste Management Program in the Department of Natural Resources regulates the management of solid waste in the state of Missouri. A permit is required prior to the construction or...

26

Waste Management Program. Technical progress report, October-December 1982  

SciTech Connect

This quarterly report provides current information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant and offplant participants. The studies on environmental and safety assessments, in situ storage or disposal, waste from development and characterization, process and equipment development, and low-level waste management are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations Program: surveillance and maintenance, waste concentration, low-level effluent waste, tank replacement/waste transfer, and solid waste storage and related activities.

None

1983-07-01T23:59:59.000Z

27

Waste Management Program. Technical progress report, Aporil-June 1983  

Science Conference Proceedings (OSTI)

This quarterly report provides current information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant. The studies on environmental and safety assessments, process and equipment development, TRU waste, and low-level waste are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations Program: surveillance and maintenance, waste concentration, low-level effluent waste, tank replacement/waste transfer, and solid waste storage and related activities.

None

1984-02-01T23:59:59.000Z

28

Using Waste Heat for External Processes  

Science Conference Proceedings (OSTI)

This DOE Industrial Technologies Program tip sheet describes the savings resulting from using waste heat from high-temperature industrial processes for lower temperature processes, like oven-drying.

Not Available

2006-01-01T23:59:59.000Z

29

Waste Management Program  

NLE Websites -- All DOE Office Websites (Extended Search)

Waste Management Facility ISO 14001 Registered A wide range of wastes are generated during the normal course of business at BNL. These waste streams are common to many businesses...

30

Site Programs & Cooperative Agreements: Waste Isolation Pilot...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Waste Isolation Pilot Plant Site Programs & Cooperative Agreements: Waste Isolation Pilot Plant Waste Isolation Pilot Plant (WIPP) The DOE Carlsbad Field Office funds a number of...

31

Mixed Waste Focus Area program management plan  

SciTech Connect

This plan describes the program management principles and functions to be implemented in the Mixed Waste Focus Area (MWFA). The mission of the MWFA is to provide acceptable technologies that enable implementation of mixed waste treatment systems developed in partnership with end-users, stakeholders, tribal governments and regulators. The MWFA will develop, demonstrate and deliver implementable technologies for treatment of mixed waste within the DOE Complex. Treatment refers to all post waste-generation activities including sampling and analysis, characterization, storage, processing, packaging, transportation and disposal.

Beitel, G.A.

1996-10-01T23:59:59.000Z

32

PROCESSING OF RADIOACTIVE WASTE  

DOE Patents (OSTI)

A process for treating radioactive waste solutions prior to disposal is described. A water-soluble phosphate, borate, and/or silicate is added. The solution is sprayed with steam into a space heated from 325 to 400 deg C whereby a powder is formed. The powder is melted and calcined at from 800 to 1000 deg C. Water vapor and gaseous products are separated from the glass formed. (AEC)

Johnson, B.M. Jr.; Barton, G.B.

1961-11-14T23:59:59.000Z

33

Waste Management Program. Technical progress report, July-December, 1984  

Science Conference Proceedings (OSTI)

This report provides information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant and offplant participants. The studies on environmental and safety assessments, other support, in situ storage or disposal, waste form development and characterization, process and equipment development, and the Defense Waste Processing Facility are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations: tank farm operation, inspection program, burial ground operations, and waste transfer/tank replacement.

None

1986-10-01T23:59:59.000Z

34

Efficient separations & processing crosscutting program  

Science Conference Proceedings (OSTI)

The Efficient Separations and Processing Crosscutting Program (ESP) was created in 1991 to identify, develop, and perfect chemical and physical separations technologies and chemical processes which treat wastes and address environmental problems throughout the DOE complex. The ESP funds several multiyear tasks that address high-priority waste remediation problems involving high-level, low-level, transuranic, hazardous, and mixed (radioactive and hazardous) wastes. The ESP supports applied research and development (R & D) leading to the demonstration or use of these separations technologies by other organizations within the Department of Energy (DOE), Office of Environmental Management.

NONE

1996-08-01T23:59:59.000Z

35

Radioactive waste processing apparatus  

DOE Patents (OSTI)

Apparatus for use in processing radioactive waste materials for shipment and storage in solid form in a container is disclosed. The container includes a top, and an opening in the top which is smaller than the outer circumference of the container. The apparatus includes an enclosure into which the container is placed, solution feed apparatus for adding a solution containing radioactive waste materials into the container through the container opening, and at least one rotatable blade for blending the solution with a fixing agent such as cement or the like as the solution is added into the container. The blade is constructed so that it can pass through the opening in the top of the container. The rotational axis of the blade is displaced from the center of the blade so that after the blade passes through the opening, the blade and container can be adjusted so that one edge of the blade is adjacent the cylindrical wall of the container, to insure thorough mixing. When the blade is inside the container, a substantially sealed chamber is formed to contain vapors created by the chemical action of the waste solution and fixant, and vapors emanating through the opening in the container.

Nelson, Robert E. (Lombard, IL); Ziegler, Anton A. (Darien, IL); Serino, David F. (Maplewood, MN); Basnar, Paul J. (Western Springs, IL)

1987-01-01T23:59:59.000Z

36

PROCESSING OF RADIOACTIVE WASTE  

DOE Patents (OSTI)

A process for concentrating fission-product-containing waste solutions from fuel element processing is described. The process comprises the addition of sugar to the solution, preferably after it is made alkaline; spraying the solution into a heated space whereby a dry powder is formed; heating the powder to at least 220 deg C in the presence of oxygen whereby the powder ignites, the sugar is converted to carbon, and the salts are decomposed by the carbon; melting the powder at between 800 and 900 deg C; and cooling the melt. (AEC) antidiuretic hormone from the blood by the liver. Data are summarized from the following: tracer studies on cardiovascular functions; the determination of serum protein-bound iodine; urinary estrogen excretion in patients with arvanced metastatic mammary carcinoma; the relationship between alheroclerosis aad lipoproteins; the physical chemistry of lipoproteins; and factors that modify the effects of densely ionizing radia

Allemann, R.T.; Johnson, B.M. Jr.

1961-10-31T23:59:59.000Z

37

Independent Oversight Review of the Fire Protection Program and Fire Protection Systems at the Transuranic Waste Processing Center, December 2013  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

and Fire Protection Systems and Fire Protection Systems at the Transuranic Waste Processing Center December 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U. S. Department of Energy Table of Contents 1.0 Purpose.................................................................................................................................................... 1 2.0 Background ............................................................................................................................................. 1 3.0 Scope....................................................................................................................................................... 2 4.0 Methodology .......................................................................................................................................... 2

38

Municipal waste processing apparatus  

DOE Patents (OSTI)

Municipal waste materials are processed by crushing the materials so that pieces of noncombustible material are smaller than a selected size and pieces of combustible material are larger than the selected size. The crushed materials are placed on a vibrating mesh screen conveyor belt having openings which pass the smaller, noncombustible pieces of material, but do not pass the larger, combustible pieces of material. Pieces of material which become lodged in the openings of the conveyor belt may be removed by cylindrical deraggers or pressurized air. The crushed materials may be fed onto the conveyor belt by a vibrating feed plate which shakes the materials so that they tend to lie flat.

Mayberry, J.L.

1987-01-15T23:59:59.000Z

39

Municipal waste processing apparatus  

DOE Patents (OSTI)

Municipal waste materials are processed by crushing the materials so that pieces of noncombustible material are smaller than a selected size and pieces of combustible material are larger than the selected size. The crushed materials are placed on a vibrating mesh screen conveyor belt having openings which pass the smaller, noncombustible pieces of material, but do not pass the larger, combustible pieces of material. Pieces of material which become lodged in the openings of the conveyor belt may be removed by cylindrical deraggers or pressurized air. The crushed materials may be fed onto the conveyor belt by a vibrating feed plate which shakes the materials so that they tend to lie flat.

Mayberry, John L. (Idaho Falls, ID)

1988-01-01T23:59:59.000Z

40

Municipal waste processing apparatus  

DOE Patents (OSTI)

Municipal waste materials are processed by crushing the materials so that pieces of noncombustible material are smaller than a selected size and pieces of combustible material are larger than the selected size. The crushed materials are placed on a vibrating mesh screen conveyor belt having openings which pass the smaller, noncombustible pieces of material, but do not pass the larger, combustible pieces of material. Consecutive conveyors may be connected by an intermediate vibratory plate. An air knife can be used to further separate materials based on weight.

Mayberry, John L. (Idaho Falls, ID)

1989-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste processing program" 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.


41

ICPP waste management technology development program  

SciTech Connect

A program has been implemented at the Idaho Chemical Processing Plant (ICPP) to identify technologies for disposing of sodium-bearing liquid radioactive waste, radioactive calcine, and irradiated spent fuel stored at the Idaho National Engineering Laboratory (INEL). The sodium bearing waste and calcine, have resulted from ICPP reprocessing operations conducted since 1953. The irradiated spent fuel consists of various fuel compositions and ranges from complete fuel elements to fuel pieces for which no reprocessing flowsheet had been identified. The program includes a very strong systems analysis program to assure complete consideration of all issues (technical, economic, safety, environmental, etc.) affecting final disposal of the waste and spent fuel. A major goal of the program is to assure the final implementation is environmentally acceptable, ensures public and worker safety, and is economically feasible.

Hogg, G.W.; Olson, A.L.; Knecht, D.A. [Westinghouse Idaho Nuclear Co., Inc., Idaho Falls, ID (United States); Bonkoski, M.J. [USDOE Idaho Field Office, Idaho Falls, ID (United States)

1993-06-01T23:59:59.000Z

42

Tank Waste Disposal Program redefinition  

SciTech Connect

The record of decision (ROD) (DOE 1988) on the Final Environmental Impact Statement, Hanford Defense High-Level, Transuranic and Tank Wastes, Hanford Site, Richland Washington identifies the method for disposal of double-shell tank waste and cesium and strontium capsules at the Hanford Site. The ROD also identifies the need for additional evaluations before a final decision is made on the disposal of single-shell tank waste. This document presents the results of systematic evaluation of the present technical circumstances, alternatives, and regulatory requirements in light of the values of the leaders and constitutents of the program. It recommends a three-phased approach for disposing of tank wastes. This approach allows mature technologies to be applied to the treatment of well-understood waste forms in the near term, while providing time for the development and deployment of successively more advanced pretreatment technologies. The advanced technologies will accelerate disposal by reducing the volume of waste to be vitrified. This document also recommends integration of the double-and single-shell tank waste disposal programs, provides a target schedule for implementation of the selected approach, and describes the essential elements of a program to be baselined in 1992.

Grygiel, M.L.; Augustine, C.A.; Cahill, M.A.; Garfield, J.S.; Johnson, M.E.; Kupfer, M.J.; Meyer, G.A.; Roecker, J.H. [Westinghouse Hanford Co., Richland, WA (United States); Holton, L.K.; Hunter, V.L.; Triplett, M.B. [Pacific Northwest Lab., Richland, WA (United States)

1991-10-01T23:59:59.000Z

43

Solid Waste Management Program Plan  

SciTech Connect

The objective of the Solid Waste Management Program Plan (SWMPP) is to provide a summary level comprehensive approach for the storage, treatment, and disposal of current and future solid waste received at the Hanford Site (from onsite and offsite generators) in a manner compliant with current and evolving regulations and orders (federal, state, and Westinghouse Hanford Company (Westinghouse Hanford)). The Plan also presents activities required for disposal of selected wastes currently in retrievable storage. The SWMPP provides a central focus for the description and control of cost, scope, and schedule of Hanford Site solid waste activities, and provides a vehicle for ready communication of the scope of those activities to onsite and offsite organizations. This Plan represents the most complete description available of Hanford Site Solid Waste Management (SWM) activities and the interfaces between those activities. It will be updated annually to reflect changes in plans due to evolving regulatory requirements and/or the SWM mission. 8 refs., 9 figs., 4 tabs.

Duncan, D.R.

1990-08-01T23:59:59.000Z

44

Radioactive waste processing apparatus  

DOE Patents (OSTI)

Apparatus for use in processing radioactive waste materials for shipment and storage in solid form in a container is disclosed. The container includes a top, and an opening in the top which is smaller than the outer circumference of the container. The apparatus includes an enclosure into which the container is placed, solution feed apparatus for adding a solution containing radioactive waste materials into the container through the container opening, and at least one rotatable blade for blending the solution with a fixing agent such as cement or the like as the solution is added into the container. The blade is constructed so that it can pass through the opening in the top of the container. The rotational axis of the blade is displaced from the center of the blade so that after the blade passes through the opening, the blade and container can be adjusted so that one edge of the blade is adjacent the cylindrical wall of the container, to insure thorough mixing. When the blade is inside the container, a substantially sealed chamber is formed to contain vapors created by the chemical action of the waste solution and fixant, and vapors emanating through the opening in the container. The chamber may be formed by placing a removable extension over the top of the container. The extension communicates with the apparatus so that such vapors are contained within the container, extension and solution feed apparatus. A portion of the chamber includes coolant which condenses the vapors. The resulting condensate is returned to the container by the force of gravity.

Nelson, R.E.; Ziegler, A.A.; Serino, D.F.; Basnar, P.J.

1985-08-30T23:59:59.000Z

45

REMOTE IN-CELL SAMPLING IMPROVEMENTS PROGRAM AT THESAVANNAH RIVER SITE (SRS) DEFENSE WASTE PROCESSING FACILITY (DWPF)  

Science Conference Proceedings (OSTI)

Remote Systems Engineering (RSE) of the Savannah River National Lab (SRNL) in combination with the Defense Waste Processing Facility(DWPF) Engineering and Operations has evaluated the existing equipment and processes used in the facility sample cells for 'pulling' samples from the radioactive waste stream and performing equipment in-cell repairs/replacements. RSE has designed and tested equipment for improving remote in-cell sampling evolutions and reducing the time required for in-cell maintenance of existing equipment. The equipment within the present process tank sampling system has been in constant use since the facility start-up over 17 years ago. At present, the method for taking samples within the sample cells produces excessive maintenance and downtime due to frequent failures relative to the sampling station equipment and manipulator. Location and orientation of many sampling stations within the sample cells is not conducive to manipulator operation. The overextension of manipulators required to perform many in-cell operations is a major cause of manipulator failures. To improve sampling operations and reduce downtime due to equipment maintenance, a Portable Sampling Station (PSS), wireless in-cell cameras, and new commercially available sampling technology has been designed, developed and/or adapted and tested. The uniqueness of the design(s), the results of the scoping tests, and the benefits relative to in-cell operation and reduction of waste are presented.

Marzolf, A

2007-11-26T23:59:59.000Z

46

MIxed Waste Integrated Program (MWIP): Technology summary  

Science Conference Proceedings (OSTI)

The mission of the Mixed Waste Integrated Program (MWIP) is to develop and demonstrate innovative and emerging technologies for the treatment and management of DOE`s mixed low-level wastes (MLLW) for use by its customers, the Office of Waste Operations (EM-30) and the Office of Environmental Restoration (EM-40). The primary goal of MWIP is to develop and demonstrate the treatment and disposal of actual mixed waste (MMLW and MTRU). The vitrification process and the plasma hearth process are scheduled for demonstration on actual radioactive waste in FY95 and FY96, respectively. This will be accomplished by sequential studies of lab-scale non-radioactive testing followed by bench-scale radioactive testing, followed by field-scale radioactive testing. Both processes create a highly durable final waste form that passes leachability requirements while destroying organics. Material handling technology, and off-gas requirements and capabilities for the plasma hearth process and the vitrification process will be established in parallel.

NONE

1994-02-01T23:59:59.000Z

47

Roadmapping Process Improvements by Experience at the Idaho National Engineering and Environmental Laboratory High Level Waste Program and Synergistic Interfaces with Decision-Making  

SciTech Connect

Six technology roadmaps were developed for various technologies under consideration for the treatment of sodium bearing liquid and calcine wastes. In the process of creating these roadmaps, a number of process improvements were identified for each of the formal roadmapping phases as described in the Department of Energy’s draft roadmapping guidance. The lessons learned, presented as beneficial improvements to the Idaho National Engineering and Environmental Laboratory (INEEL) High Level Waste Program, are proposed to be added to the draft guidance. Additionally, synergistic interfaces between the roadmapping and decision-making processes were observed and reported on. With these improvements, technology roadmapping has become an effective integration tool at the INEEL for planning technology development.

Murphy, James Anthony; Olson, Arlin Leland

2001-02-01T23:59:59.000Z

48

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM - 2011  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2011 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2011 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per SRR-LWE-2011-00026, HLW Tank Farm Inspection Plan for 2011, were completed. Ultrasonic measurements (UT) performed in 2011 met the requirements of C-ESR-G-00006, In-Service Inspection Program for High Level Waste Tanks, Rev. 3, and WSRC-TR-2002-00061, Rev.6. UT inspections were performed on Tanks 25, 26 and 34 and the findings are documented in SRNL-STI-2011-00495, Tank Inspection NDE Results for Fiscal Year 2011, Waste Tanks 25, 26, 34 and 41. A total of 5813 photographs were made and 835 visual and video inspections were performed during 2011. A potential leaksite was discovered at Tank 4 during routine annual inspections performed in 2011. The new crack, which is above the allowable fill level, resulted in no release to the environment or tank annulus. The location of the crack is documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.6.

West, B.; Waltz, R.

2012-06-21T23:59:59.000Z

49

New Facility Saves $20 Million, Accelerates Waste Processing | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Facility Saves $20 Million, Accelerates Waste Processing Facility Saves $20 Million, Accelerates Waste Processing New Facility Saves $20 Million, Accelerates Waste Processing August 15, 2012 - 12:00pm Addthis The new Cask Processing Enclosure (CPE) facility is located at the Transuranic Waste Processing Center (TWPC). The Transuranic Waste Processing Center (TWPC) processes, repackages, and ships the site's legacy TRU waste offsite. OAK RIDGE, Tenn. - Oak Ridge's EM program recently began operations at a newly constructed facility that will accelerate the completion of remote-handled transuranic (TRU) waste processing at the site by two years and save taxpayers more than $20 million. The new Cask Processing Enclosure (CPE) facility is located at the Transuranic Waste Processing Center (TWPC). TWPC processes, repackages, and

50

Heterogeneous waste processing  

DOE Patents (OSTI)

A combination of treatment methods are provided for treatment of heterogeneous waste including: (1) treatment for any organic compounds present; (2) removal of metals from the waste; and, (3) bulk volume reduction, with at least two of the three treatment methods employed and all three treatment methods emplyed where suitable.

Vanderberg, Laura A. (Los Alamos, NM); Sauer, Nancy N. (Los Alamos, NM); Brainard, James R. (Los Alamos, NM); Foreman, Trudi M. (Los Alamos, NM); Hanners, John L. (Los Alamos, NM)

2000-01-01T23:59:59.000Z

51

Tank Waste and Waste Processing | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

52

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2010  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2010 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2010 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per SRR-LWE-2009-00138, HLW Tank Farm Inspection Plan for 2010, were completed. Ultrasonic measurements (UT) performed in 2010 met the requirements of C-ESG-00006, In-Service Inspection Program for High Level Waste Tanks, Rev. 3, and WSRC-TR-2002-00061, Rev.6. UT inspections were performed on Tanks 30, 31 and 32 and the findings are documented in SRNL-STI-2010-00533, Tank Inspection NDE Results for Fiscal Year 2010, Waste Tanks 30, 31 and 32. A total of 5824 photographs were made and 1087 visual and video inspections were performed during 2010. Ten new leaksites at Tank 5 were identified in 2010. The locations of these leaksites are documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.5. Ten leaksites at Tank 5 were documented during tank wall/annulus cleaning activities. None of these new leaksites resulted in a release to the environment. The leaksites were documented during wall cleaning activities and the waste nodules associated with the leaksites were washed away. Previously documented leaksites were reactivated at Tank 12 during waste removal activities.

West, B.; Waltz, R.

2011-06-23T23:59:59.000Z

53

The Remote-Handled TRU Waste Program  

SciTech Connect

RH TRU Waste is radioactive waste that requires shielding in addition to that provided by the container to protect people nearby from radiation exposure. By definition, the radiation dose rate at the outer surface of the container is greater than 200 millirem per hour and less than 1,000 rem per hour. The DOE is proposing a process for the characterization of RH TRU waste planned for disposal in the WIPP. This characterization process represents a performance-driven approach that satisfies the requirements of the New Mexico Hazardous Waste Act, the Environmental Protection Agency (EPA) regulations for WIPP long-term performance, the transportation requirements of the Nuclear Regulatory Commission (NRC) and the Department of Transportation, as well as the technical safety requirements of RH TRU waste handling. The transportation, management and disposal of RH TRU waste is regulated by external government agencies as well as by the DOE itself. Externally, the characterization of RH-TRU waste for disposal at the WIPP is regulated by 20.4.1.500 New Mexico Administrative Code (incorporating 40 CFR 261.13) for the hazardous constituents and 40 CFR 194.24 for the radioactive constituents. The Nuclear Regulatory Commission certifies the shipping casks and the transportation system must meet DOT regulations. Internally, the DOE evaluates the environmental impacts of RH TRU waste transportation, handling and disposal through its National Environmental Policy Act program. The operational safety is assessed in the RH TRU Waste Safety Analysis Report, to be approved by the DOE. The WIPP has prepared a modification request to the Hazardous Waste Facility Permit that includes modifications to the WIPP facility for the safe receipt and handling of RH TRU waste and the addition of an RH TRU waste analysis plan. Modifications to the facility include systems and equipment for safe handling of RHTRU containers. Two shipping casks are to be used to optimize RH TRU was te throughput: the RH-72B and the CNS 10-160B transportation casks. Additionally, a draft Notification of Proposed Change to the EPA 40 CFR 194 Certification of the WIPP has been prepared, which contains a proposal for the RH TRU characterization program for compliance with the EPA requirements.

Gist, C. S.; Plum, H. L.; Wu, C. F.; Most, W. A.; Burrington, T. P.; Spangler, L. R.

2002-02-26T23:59:59.000Z

54

Grand Junction projects office mixed-waste treatment program, VAC*TRAX mobile treatment unit process hazards analysis  

SciTech Connect

The objective of this report is to demonstrate that a thorough assessment of the risks associated with the operation of the Rust Geotech patented VAC*TRAX mobile treatment unit (MTU) has been performed and documented. The MTU was developed to treat mixed wastes at the US Department of Energy (DOE) Albuquerque Operations Office sites. The MTU uses an indirectly heated, batch vacuum dryer to thermally desorb organic compounds from mixed wastes. This process hazards analysis evaluated 102 potential hazards. The three significant hazards identified involved the inclusion of oxygen in a process that also included an ignition source and fuel. Changes to the design of the MTU were made concurrent with the hazard identification and analysis; all hazards with initial risk rankings of 1 or 2 were reduced to acceptable risk rankings of 3 or 4. The overall risk to any population group from operation of the MTU was determined to be very low; the MTU is classified as a Radiological Facility with low hazards.

Bloom, R.R.

1996-04-01T23:59:59.000Z

55

Emergency Management Program Review at the Waste Isolation Pilot Plant  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Waste Waste Isolation Pilot Plant Emergency Management Program Review at the May 2000 OVERSIGHT Table of Contents EXECUTIVE SUMMARY ................................................................... 1 1.0 INTRODUCTION ........................................................................... 4 2.0 RESULTS ......................................................................................... 6 Hazards Survey and Hazards Assessments .................................. 6 Program Plans, Procedures, and Responder Performance ........ 9 Training, Drills, and Exercises ..................................................... 13 Emergency Public Information and Offsite Response Interfaces ....................................................................................... 15 Feedback and Continuous Improvement Process

56

Mixed wasted integrated program: Logic diagram  

SciTech Connect

The Mixed Waste Integrated Program Logic Diagram was developed to provide technical alternative for mixed wastes projects for the Office of Technology Development`s Mixed Waste Integrated Program (MWIP). Technical solutions in the areas of characterization, treatment, and disposal were matched to a select number of US Department of Energy (DOE) treatability groups represented by waste streams found in the Mixed Waste Inventory Report (MWIR).

Mayberry, J.; Stelle, S. [Science Applications International Corp., Idaho Falls, ID (United States); O`Brien, M. [Univ. of Arizona, Tucson, AZ (United States); Rudin, M. [Univ. of Nevada, Las Vegas, NV (United States); Ferguson, J. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); McFee, J. [I.T. Corp., Albuquerque, NM (United States)

1994-11-30T23:59:59.000Z

57

SRNL PHASE 1 ASSESSMENT OF THE WTP WASTE QUALIFICATION PROGRAM  

SciTech Connect

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) Project is currently transitioning its emphasis from an engineering design and construction phase toward facility completion, start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements that must be met during the actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program. In general, the waste qualification program involves testing and analysis to demonstrate compliance with waste acceptance criteria, determine waste processability, and demonstrate laboratory-scale unit operations to support WTP operations. The testing and analysis are driven by data quality objectives (DQO) requirements necessary for meeting waste acceptance criteria for transfer of high-level wastes from the tank farms to the WTP, and for ensuring waste processability including proper glass formulations during processing within the WTP complex. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS) which were based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested subject matter experts (SMEs) from SRNL to support a technology exchange with respect to waste qualification programs in which a critical review of the WTP program could be initiated and lessons learned could be shared. The technology exchange was held on July 18-20, 2011 in Richland, Washington, and was the initial step in a multi-phased approach to support development and implementation of a successful waste qualification program at the WTP. The 3-day workshop was hosted by WTP with representatives from the Tank Operations Contractor (TOC) and SRNL in attendance as well as representatives from the US DOE Office of River Protection (ORP) and the Defense Nuclear Facility Safety Board (DNFSB) Site Representative office. The purpose of the workshop was to share lessons learned and provide a technology exchange to support development of a technically defensible waste qualification program. The objective of this report is to provide a review, from SRNL's perspective, of the WTP waste qualification program as presented during the workshop. In addition to SRNL's perspective on the general approach to the waste qualification program, more detailed insight into the specific unit operations presented by WTP during the workshop is provided. This report also provides a general overview of the SRS qualification program which serves as a basis for a comparison between the two programs. Recommendations regarding specific steps are made based on the review and SRNL's lessons learned from qualification of SRS low-activity waste (LAW) and high-level waste (HLW) to support maturation of the waste qualification program leading to WTP implementation.

Peeler, D.; Hansen, E.; Herman, C.; Marra, S.; Wilmarth, B.

2012-03-06T23:59:59.000Z

58

Method for processing aqueous wastes  

DOE Patents (OSTI)

This invention is comprised of a method for treating waste water such as that from an industrial processing facility comprising the separation of the waste water into a dilute waste stream and a concentrated waste stream. The concentrated waste stream is treated chemically to enhance precipitation and then allowed to separate into a sludge and a supernate. The supernate is skimmed or filtered from the sludge and blended with the dilute waste stream to form a second dilute waste stream. The sludge remaining is mixed with cementitious material, rinsed to dissolve soluble components, then pressed to remove excess water and dissolved solids before being allowed to cure. The dilute waste stream is also chemically treated to decompose carbonate complexes and metal ions and then mixed with cationic polymer to cause the precipitated solids to flocculate. Filtration of the flocculant removes sufficient solids to allow the waste water to be discharged to the surface of a stream. The filtered material is added to the sludge of the concentrated waste stream. The method is also applicable to the treatment and removal of soluble uranium from aqueous streams, such that the treated stream may be used as a potable water supply.

Pickett, J.B.; Martin, H.L.; Langton, C.A.; Harley, W.W.

1992-12-31T23:59:59.000Z

59

Method for processing aqueous wastes  

DOE Patents (OSTI)

A method is presented for treating waste water such as that from an industrial processing facility comprising the separation of the waste water into a dilute waste stream and a concentrated waste stream. The concentrated waste stream is treated chemically to enhance precipitation and then allowed to separate into a sludge and a supernate. The supernate is skimmed or filtered from the sludge and blended with the dilute waste stream to form a second dilute waste stream. The sludge remaining is mixed with cementitious material, rinsed to dissolve soluble components, then pressed to remove excess water and dissolved solids before being allowed to cure. The dilute waste stream is also chemically treated to decompose carbonate complexes and metal ions and then mixed with cationic polymer to cause the precipitated solids to flocculate. Filtration of the flocculant removes sufficient solids to allow the waste water to be discharged to the surface of a stream. The filtered material is added to the sludge of the concentrated waste stream. The method is also applicable to the treatment and removal of soluble uranium from aqueous streams, such that the treated stream may be used as a potable water supply. 4 figures.

Pickett, J.B.; Martin, H.L.; Langton, C.A.; Harley, W.W.

1993-12-28T23:59:59.000Z

60

Method for processing aqueous wastes  

DOE Patents (OSTI)

A method for treating waste water such as that from an industrial processing facility comprising the separation of the waste water into a dilute waste stream and a concentrated waste stream. The concentrated waste stream is treated chemically to enhance precipitation and then allowed to separate into a sludge and a supernate. The supernate is skimmed or filtered from the sludge and blended with the dilute waste stream to form a second dilute waste stream. The sludge remaining is mixed with cementitious material, rinsed to dissolve soluble components, then pressed to remove excess water and dissolved solids before being allowed to cure. The dilute waste stream is also chemically treated to decompose carbonate complexes and metal ions and then mixed with cationic polymer to cause the precipitated solids to flocculate. Filtration of the flocculant removes sufficient solids to allow the waste water to be discharged to the surface of a stream. The filtered material is added to the sludge of the concentrated waste stream. The method is also applicable to the treatment and removal of soluble uranium from aqueous streams, such that the treated stream may be used as a potable water supply.

Pickett, John B. (3922 Wood Valley Dr., Aiken, SC 29803); Martin, Hollis L. (Rt. 1, Box 188KB, McCormick, SC 29835); Langton, Christine A. (455 Sumter St. SE., Aiken, SC 29801); Harley, Willie W. (110 Fairchild St., Batesburg, SC 29006)

1993-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste processing program" 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

Oak Ridge National Laboratory TRU Waste Processing Center Tank Waste Processing Supernate Processing System  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

TRU Waste Processing Center TRU Waste Processing Center ORNL TRU Waste Processing Center Tank Waste Processing Supernate (SN) Processing System Presented by Don F. Gagel Vice President and Chief Technology Officer EnergX LLC ORNL TRU Waste Processing Center 1/21/09 2 SRS Technology Transfer, ORNL SN Process Overview SN Process Facility ORNL TRU Waste Processing Center 3 Waste Concentration Using Evaporator Evaporator Concentrates Waste Vapor stream superheated and HEPA-filtered Vapor stream exhausted to main ventilation system Supernate Pump and Evaporator Discharge Pump circulate waste between selected tank and evaporator during concentration. Evaporator Discharge Pump Supernate Pump Supernate Tank Evaporator Exhaust Blower ORNL TRU Waste Processing Center 4 Tank Sampling/ Transfer To Dryer Tank

62

TRU Waste Sampling Program: Volume I. Waste characterization  

DOE Green Energy (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

63

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM- 2007  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. The 2007 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. A very small amount of material had seeped from Tank 12 from a previously identified leaksite. The material observed had dried on the tank wall and did not reach the annulus floor. A total of 5945 photographs were made and 1221 visual and video inspections were performed during 2007. Additionally, ultrasonic testing was performed on four Waste Tanks (15, 36, 37 and 38) in accordance with approved inspection plans that met the requirements of WSRC-TR-2002- 00061, Revision 2 'In-Service Inspection Program for High Level Waste Tanks'. The Ultrasonic Testing (UT) In-Service Inspections (ISI) are documented in a separate report that is prepared by the ISI programmatic Level III UT Analyst. Tanks 15, 36, 37 and 38 are documented in 'Tank Inspection NDE Results for Fiscal Year 2007'; WSRC-TR-2007-00064.

West, B; Ruel Waltz, R

2008-06-05T23:59:59.000Z

64

Zero Waste Program 2011 Recycling Benefits  

E-Print Network (OSTI)

of the following homes per month: 10,343 286 tons of plastic 95 tons of aluminum 0 KW-Hrs of Electricity from Waste-to-Energy: This provides enough energy to heat and cool at a Waste-to-Energy (WTE) the following homes per month: 10Rutgers Zero Waste Program 2011 Recycling Benefits Through WM's Recycling Program, our company

Delgado, Mauricio

65

Animal Waste Treatment System Loan Program (Missouri)  

Energy.gov (U.S. Department of Energy (DOE))

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

66

Status of Waste Processing Technology Development  

Radiation stability testing on sRF Evaluated and selected potential ... Technical reports Tests with real waste Program performance reviews

67

Chapter 38 Hazardous Waste Permitting Process (Kentucky) | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

8 Hazardous Waste Permitting Process (Kentucky) 8 Hazardous Waste Permitting Process (Kentucky) Chapter 38 Hazardous Waste Permitting Process (Kentucky) < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Industrial Institutional Investor-Owned Utility Local Government Municipal/Public Utility Rural Electric Cooperative Schools State/Provincial Govt Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Program Info State Kentucky Program Type Environmental Regulations Provider Department for Environmental Protection This administrative regulation establishes the general provisions for storage, treatment, recycling, or disposal of hazardous waste. It provides information about permits and specific requirements for containers, tanks,

68

Improved FGD dewatering process cuts solid wastes  

Science Conference Proceedings (OSTI)

In 2007, Duke Energy's W.H. Zimmer Station set out to advance the overall performance of its flue gas desulfurization (FGD) dewatering process. The plant implemented a variety of measures, including upgrading water-solids separation, improving polymer program effectiveness and reliability, optimizing treatment costs, reducing solid waste sent to the landfill, decreasing labor requirements, and maintaining septic-free conditions in clarifiers. The changes succeeded in greatly reducing solid waste generation and achieving total annual savings of over half a million dollars per year. 8 figs., 1 tab.

Moer, C.; Fernandez, J.; Carraro, B. [Duke Energy (United States)

2009-08-15T23:59:59.000Z

69

SRS - Programs - Solid Waste Management  

NLE Websites -- All DOE Office Websites (Extended Search)

manner possible. SRS's waste is categorized as transuranic, low-level, hazardous, mixed, high-level or sanitary waste. SWM is responsible for managing all of these...

70

Solid Waste Program (Alabama) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

71

Quality Assurance Program Plan (QAPP) Waste Management Project  

SciTech Connect

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

72

Mixed Waste Integrated Program -- Problem-oriented technology development  

SciTech Connect

The Mixed Waste Integrated Program (MWIP) is responding to the need for DOE mixed waste treatment technologies that meet these dual regulatory requirements. MWIP is developing emerging and innovative treatment technologies to determine process feasibility. Technology demonstrations will be used to determine whether processes are superior to existing technologies in reducing risk, minimizing life-cycle cost, and improving process performance. Technology development is ongoing in technical areas required to process mixed waste: materials handling, chemical/physical treatment, waste destruction, off-gas treatment, final forms, and process monitoring/control. MWIP is currently developing a suite of technologies to process heterogeneous waste. One robust process is the fixed-hearth plasma-arc process that is being developed to treat a wide variety of contaminated materials with minimal characterization. Additional processes encompass steam reforming, including treatment of waste under the debris rule. Advanced off-gas systems are also being developed. Vitrification technologies are being demonstrated for the treatment of homogeneous wastes such as incinerator ash and sludge. An alternative to conventional evaporation for liquid removal--freeze crystallization--is being investigated. Since mercury is present in numerous waste streams, mercury removal technologies are being developed.

Hart, P.W.; Wolf, S.W. [Dept. of Energy, Germantown, MD (United States); Berry, J.B. [Oak Ridge National Lab., TN (United States). Chemical Technology Div.

1994-12-31T23:59:59.000Z

73

Solid Waste Management Program (South Dakota) | Department of...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Other Agencies You are here Home Savings Solid Waste Management Program (South Dakota) Solid Waste Management Program (South Dakota) Eligibility Utility Fed....

74

Fuel cycle and waste management demonstration in the IFR Program  

Science Conference Proceedings (OSTI)

Argonne's National Laboratory's Integral Fast Reactor (IFR) is the main element in the US advanced reactor development program. A unique fuel cycle and waste process technology is being developed for the IFR. Demonstration of this technology at engineering scale will begin within the next year at the EBR-II test facility complex in Idaho. This paper describes the facility being readied for this demonstration, the process to be employed, the equipment being built, and the waste management approach.

Lineberry, M.J.; Phipps, R.D.; Benedict, R.W. (Argonne National Lab., Idaho Falls, ID (United States)); Laidler, J.J.; Battles, J.E.; Miller, W.E. (Argonne National Lab., IL (United States))

1992-01-01T23:59:59.000Z

75

Fuel cycle and waste management demonstration in the IFR Program  

SciTech Connect

Argonne`s National Laboratory`s Integral Fast Reactor (IFR) is the main element in the US advanced reactor development program. A unique fuel cycle and waste process technology is being developed for the IFR. Demonstration of this technology at engineering scale will begin within the next year at the EBR-II test facility complex in Idaho. This paper describes the facility being readied for this demonstration, the process to be employed, the equipment being built, and the waste management approach.

Lineberry, M.J.; Phipps, R.D.; Benedict, R.W. [Argonne National Lab., Idaho Falls, ID (United States); Laidler, J.J.; Battles, J.E.; Miller, W.E. [Argonne National Lab., IL (United States)

1992-09-01T23:59:59.000Z

76

Commercial radioactive waste minimization program development guidance  

SciTech Connect

This document is one of two prepared by the EG G Idaho, Inc., Waste Management Technical Support Program Group, National Low-Level Waste Management Program Unit. One of several Department of Energy responsibilities stated in the Amendments Act of 1985 is to provide technical assistance to compact regions Host States, and nonmember States (to the extent provided in appropriations acts) in establishing waste minimization program plans. Technical assistance includes, among other things, the development of technical guidelines for volume reduction options. Pursuant to this defined responsibility, the Department of Energy (through EG G Idaho, Inc.) has prepared this report, which includes guidance on defining a program, State/compact commission participation, and waste minimization program plans.

Fischer, D.K.

1991-01-01T23:59:59.000Z

77

Commercial radioactive waste minimization program development guidance  

SciTech Connect

This document is one of two prepared by the EG&G Idaho, Inc., Waste Management Technical Support Program Group, National Low-Level Waste Management Program Unit. One of several Department of Energy responsibilities stated in the Amendments Act of 1985 is to provide technical assistance to compact regions Host States, and nonmember States (to the extent provided in appropriations acts) in establishing waste minimization program plans. Technical assistance includes, among other things, the development of technical guidelines for volume reduction options. Pursuant to this defined responsibility, the Department of Energy (through EG&G Idaho, Inc.) has prepared this report, which includes guidance on defining a program, State/compact commission participation, and waste minimization program plans.

Fischer, D.K.

1991-01-01T23:59:59.000Z

78

Addressing mixed waste in plutonium processing  

SciTech Connect

The overall goal is the minimization of all waste generated in actinide processing facilities. Current emphasis is directed toward reducing and managing mixed waste in plutonium processing facilities. More specifically, the focus is on prioritizing plutonium processing technologies for development that will address major problems in mixed waste management. A five step methodological approach to identify, analyze, solve, and initiate corrective action for mixed waste problems in plutonium processing facilities has been developed.

Christensen, D.C.; Sohn, C.L. (Los Alamos National Lab., NM (United States)); Reid, R.A. (New Mexico Univ., Albuquerque, NM (United States). Anderson Schools of Management)

1991-01-01T23:59:59.000Z

79

Independent Oversight Review, Oak Ridge Transuranic Waste Processing  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Oak Ridge Transuranic Waste Oak Ridge Transuranic Waste Processing Facility - December 2013 Independent Oversight Review, Oak Ridge Transuranic Waste Processing Facility - December 2013 December 2013 Review of the Fire Protection Program and Fire Protection Systems at the Transuranic Waste Processing Center This report documents the results of an independent oversight review of the fire protection programs and systems at the Oak Ridge Transuranic Waste Processing Center. The review was performed during May 20-23, 2013, and July 15-19, 2013, by the U.S. Department of Energy's (DOE) Office of Safety and Emergency Management Evaluations, which is within the DOE Office of Health, Safety and Security. The review was one part of a targeted assessment of fire protection at nuclear facilities across the DOE complex.

80

Technical resource document for assured thermal processing of wastes  

Science Conference Proceedings (OSTI)

This document is a concise compendium of resource material covering assured thermal processing of wastes (ATPW), an area in which Sandia aims to develop a large program. The ATPW program at Sandia is examining a wide variety of waste streams and thermal processes. Waste streams under consideration include municipal, chemical, medical, and mixed wastes. Thermal processes under consideration range from various incineration technologies to non-incineration processes such as supercritical water oxidation or molten metal technologies. Each of the chapters describes the element covered, discusses issues associated with its further development and/or utilization, presents Sandia capabilities that address these issues, and indicates important connections to other ATPW elements. The division of the field into elements was driven by the team`s desire to emphasize areas where Sandia`s capabilities can lead to major advances and is therefore somewhat unconventional. The report will be valuable to Sandians involved in further ATPW program development.

Farrow, R.L.; Fisk, G.A.; Hartwig, C.M.; Hurt, R.H.; Ringland, J.T.; Swansiger, W.A.

1994-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste processing program" 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

WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION  

NLE Websites -- All DOE Office Websites (Extended Search)

Carlsbad, New Mexico 8822 Carlsbad, New Mexico 8822 1 NOV 2 3 2011 Mr. John Kieling , Acting Bureau Chief Hazardous Waste Bureau New Mexico Environme nt Department 2905 Rodeo Park Drive East, Building 1 Santa Fe, New Mexico 87505-6303 Subject: Transmittal of the Waste Isolation Pilot Plant Annual Waste Minimization Report Dear Mr. Kieling: This letter provides the submittal of the Waste Isolation Pilot Plant Annual Waste Minimization Report. This report is required by and has bee n prepared in accordance with the WIPP Hazardous Waste Facility Perm it Part 2, Permit Condition 2.4. We certify under penalty of law that this document and all enclosures were prepared under our direction or supervision according to a system designed to assure that qualified personnel properly gather and evaluate the information submitted

82

Training Program EHS 0611 ~ Universal Waste Regulatory Training  

NLE Websites -- All DOE Office Websites (Extended Search)

Environment, Health, & Safety Training Program EHS 0611 Universal Waste Regulatory Training Course Syllabus Subject...

83

Independent Oversight Review, Oak Ridge Transuranic Waste Processing  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Oak Ridge Transuranic Waste Oak Ridge Transuranic Waste Processing Center, September 2013 Independent Oversight Review, Oak Ridge Transuranic Waste Processing Center, September 2013 September 2013 Review of Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and Associated Feedback and Improvement Processes. This report documents the results of an independent oversight review of the management of safety significant structures, systems, and components at the Oak Ridge Transuranic Waste Processing Center (TWPC). The review was performed April 2-5, April 15-19, and May 19-23, 2013, by the Department of Energy's (DOE) Office of Safety and Emergency Management Evaluations, which is within the DOE Office of Health, Safety and Security. The review was carried out within the broader context of an ongoing program of

84

National waste terminal storage program  

SciTech Connect

An overview is provided of the national geologic disposal program. The portions of the program concerning South Dakota are discussed in detail. (LK)

Zerby, C.D.

1976-10-07T23:59:59.000Z

85

WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION  

NLE Websites -- All DOE Office Websites (Extended Search)

is required by and has bee n prepared in accordance with the WIPP Hazardous Waste Facility Perm it Part 2, Permit Condition 2.4. We certify under penalty of law that this...

86

INEEL Radioactive Liquid Waste Reduction Program  

SciTech Connect

Reduction of radioactive liquid waste, much of which is Resource Conservation and Recovery Act (RCRA) listed, is a high priority at the Idaho National Technology and Engineering Center (INTEC). Major strides in the past five years have lead to significant decreases in generation and subsequent reduction in the overall cost of treatment of these wastes. In 1992, the INTEC, which is part of the Idaho National Environmental and Engineering Laboratory (INEEL), began a program to reduce the generation of radioactive liquid waste (both hazardous and non-hazardous). As part of this program, a Waste Minimization Plan was developed that detailed the various contributing waste streams, and identified methods to eliminate or reduce these waste streams. Reduction goals, which will reduce expected waste generation by 43%, were set for five years as part of this plan. The approval of the plan led to a Waste Minimization Incentive being put in place between the Department of Energy–Idaho Office (DOE-ID) and the INEEL operating contractor, Lockheed Martin Idaho Technologies Company (LMITCO). This incentive is worth $5 million dollars from FY-98 through FY-02 if the waste reduction goals are met. In addition, a second plan was prepared to show a path forward to either totally eliminate all radioactive liquid waste generation at INTEC by 2005 or find alternative waste treatment paths. Historically, this waste has been sent to an evaporator system with the bottoms sent to the INTEC Tank Farm. However, this Tank Farm is not RCRA permitted for mixed wastes and a Notice of Non-compliance Consent Order gives dates of 2003 and 2012 for removal of this waste from these tanks. Therefore, alternative treatments are needed for the waste streams. This plan investigated waste elimination opportunities as well as treatment alternatives. The alternatives, and the criteria for ranking these alternatives, were identified through Value Engineering meetings with all of the waste generators. The most promising alternatives were compared by applying weighting factors to each based on how well the alternative met the established criteria. From this information, an overall ranking of the various alternatives was obtained and a path forward recommended.

Tripp, Julia Lynn; Archibald, Kip Ernest; Argyle, Mark Don; Demmer, Ricky Lynn; Miller, Rose Anna; Lauerhass, Lance

1999-03-01T23:59:59.000Z

87

INEEL Radioactive Liquid Waste Reduction Program  

SciTech Connect

Reduction of radioactive liquid waste, much of which is Resource Conservation and Recovery Act (RCRA) listed, is a high priority at the Idaho National Technology and Engineering Center (INTEC). Major strides in the past five years have lead to significant decreases in generation and subsequent reduction in the overall cost of treatment of these wastes. In 1992, the INTEC, which is part of the Idaho National Environmental and Engineering Laboratory (INEEL), began a program to reduce the generation of radioactive liquid waste (both hazardous and non-hazardous). As part of this program, a Waste Minimization Plan was developed that detailed the various contributing waste streams, and identified methods to eliminate or reduce these waste streams. Reduction goals, which will reduce expected waste generation by 43%, were set for five years as part of this plan. The approval of the plan led to a Waste Minimization Incentive being put in place between the Department of Energy ? Idaho Office (DOE-ID) and the INEEL operating contractor, Lockheed Martin Idaho Technologies Company (LMITCO). This incentive is worth $5 million dollars from FY-98 through FY-02 if the waste reduction goals are met. In addition, a second plan was prepared to show a path forward to either totally eliminate all radioactive liquid waste generation at INTEC by 2005 or find alternative waste treatment paths. Historically, this waste has been sent to an evaporator system with the bottoms sent to the INTEC Tank Farm. However, this Tank Farm is not RCRA permitted for mixed wastes and a Notice of Non-compliance Consent Order gives dates of 2003 and 2012 for removal of this waste from these tanks. Therefore, alternative treatments are needed for the waste streams. This plan investigated waste elimination opportunities as well as treatment alternatives. The alternatives, and the criteria for ranking these alternatives, were identified through Value Engineering meetings with all of the waste generators. The most promising alternatives were compared by applying weighting factors to each based on how well the alternative met the established criteria. From this information, an overall ranking of the various alternatives was obtained and a path forward recommended.

C. B. Millet; J. L. Tripp; K. E. Archibald; L. Lauerhauss; M. D. Argyle; R. L. Demmer

1999-02-01T23:59:59.000Z

88

Solid Waste Program technical baseline description  

SciTech Connect

The system engineering approach has been taken to describe the technical baseline under which the Solid Waste Program is currently operating. The document contains a mission analysis, function analysis, system definition, documentation requirements, facility and project bases, and uncertainties facing the program.

Carlson, A.B.

1994-07-01T23:59:59.000Z

89

ORISE: Process and Program Evaluation  

NLE Websites -- All DOE Office Websites (Extended Search)

Process and Program Evaluation As an integral part of producing effective health and safety programs, the Oak Ridge Institute for Science and Education (ORISE) conducts...

90

Process for remediation of plastic waste  

DOE Patents (OSTI)

A single step process for degrading plastic waste by converting the plastic waste into carbonaceous products via thermal decomposition of the plastic waste by placing the plastic waste into a reactor, heating the plastic waste under an inert or air atmosphere until the temperature of 700.degree. C. is achieved, allowing the reactor to cool down, and recovering the resulting decomposition products therefrom. The decomposition products that this process yields are carbonaceous materials, and more specifically egg-shaped and spherical-shaped solid carbons. Additionally, in the presence of a transition metal compound, this thermal decomposition process produces multi-walled carbon nanotubes.

Pol, Vilas G. (Westmont, IL); Thiyagarajan, Pappannan (Germantown, MD)

2012-04-10T23:59:59.000Z

91

Process for remediation of plastic waste  

SciTech Connect

A single step process for degrading plastic waste by converting the plastic waste into carbonaceous products via thermal decomposition of the plastic waste by placing the plastic waste into a reactor, heating the plastic waste under an inert or air atmosphere until the temperature of about 700.degree. C. is achieved, allowing the reactor to cool down, and recovering the resulting decomposition products therefrom. The decomposition products that this process yields are carbonaceous materials, and more specifically carbon nanotubes having a partially filled core (encapsulated) adjacent to one end of the nanotube. Additionally, in the presence of a transition metal compound, this thermal decomposition process produces multi-walled carbon nanotubes.

Pol, Vilas G; Thiyagarajan, Pappannan

2013-11-12T23:59:59.000Z

92

HANFORD'S SIMULATED LOW ACTIVITY WASTE CAST STONE PROCESSING  

SciTech Connect

Cast Stone is undergoing evaluation as the supplemental treatment technology for Hanford’s (Washington) high activity waste (HAW) and low activity waste (LAW). This report will only cover the LAW Cast Stone. The programs used for this simulated Cast Stone were gradient density change, compressive strength, and salt waste form phase identification. Gradient density changes show a favorable outcome by showing uniformity even though it was hypothesized differently. Compressive strength exceeded the minimum strength required by Hanford and greater compressive strength increase seen between the uses of different salt solution The salt waste form phase is still an ongoing process as this time and could not be concluded.

Kim, Y.

2013-08-20T23:59:59.000Z

93

Co-processing of agricultural and biomass waste with coal  

Science Conference Proceedings (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

94

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2008  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2008 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report.

West, B.; Waltz, R.

2009-06-11T23:59:59.000Z

95

Annual Radioactive Waste Tank Inspection Program - 2000  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2000 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report.

West, W.R.

2001-04-17T23:59:59.000Z

96

Process for treating fission waste  

DOE Patents (OSTI)

A method is described for the treatment of fission waste. A glass forming agent, a metal oxide, and a reducing agent are mixed with the fission waste and the mixture is heated. After melting, the mixture separates into a glass phase and a metal phase. The glass phase may be used to safely store the fission waste, while the metal phase contains noble metals recovered from the fission waste.

Rohrmann, Charles A. (Kennewick, WA); Wick, Oswald J. (Richland, WA)

1983-01-01T23:59:59.000Z

97

Office of Waste Processing Technical Exchange  

NLE Websites -- All DOE Office Websites (Extended Search)

Contact Information: For more EM Waste Processing Technical Exchange 2010 information, please contact one of the folowing (click name to email): Bill Wilmarth Rosalind Blocker...

98

Office of Waste Processing Technical Exchange  

... Savannah River/Hanford/Idaho along with others receiving funding from the Environmental Management Office of Waste Processing have met to exchange ...

99

Office of Waste Processing Technical Exchange  

... Savannah River/Hanford/Idaho along with others receiving funding from the Environmental Management Office of Waste Processing have met to exchange recent ...

100

Lab Ahead of Schedule Processing Waste in Large Boxes | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Lab Ahead of Schedule Processing Waste in Large Boxes Lab Ahead of Schedule Processing Waste in Large Boxes Lab Ahead of Schedule Processing Waste in Large Boxes March 30, 2012 - 12:00pm Addthis A framework agreement between DOE and the State of New Mexico calls for the Lab’s TRU Waste Program to ship 3,706 cubic meters of combustible or dispersible transuranic waste to WIPP for permanent disposal by June 30, 2014. A framework agreement between DOE and the State of New Mexico calls for the Lab's TRU Waste Program to ship 3,706 cubic meters of combustible or dispersible transuranic waste to WIPP for permanent disposal by June 30, 2014. Processing waste in large boxes is ahead of schedule due to worker skill, efficient processing and good planning. Processing waste in large boxes is ahead of schedule due to worker skill,

Note: This page contains sample records for the topic "waste processing program" 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

Nuclear waste treatment program: Annual report for FY 1987  

SciTech Connect

Two of the US Department of Energy's (DOE) nuclear waste management-related goals are to ensure that waste management is not an obstacle to the further development of light-water reactors and the closure of the nuclear fuel cycle and to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Remedial Action and Waste Technology of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting assistance, as required to treat existing wastes. This annual report describes progress during FY 1987 towards meeting these two objectives. 24 refs., 59 figs., 24 tabs.

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

1988-09-01T23:59:59.000Z

102

EM-21 Multi-Year Program Plan Prioritization Process  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

July 24, 2008 July 24, 2008 EM-21 Multi-Year Program Plan Prioritization Process A presentation to the Department of Energy High Level Waste Corporate Board 2 Topics to be Covered ¡ Initiative Development Team approach and structure ¡ Goals ¡ Background on prioritization process ¡ Lessons Learned from FY 2008 ¡ Prioritization Process l Overview l Criteria l Task Development and Selection l Current status l Process output ¡ Program Management 3 Waste Processing Programs Initiative Development Team Structure Waste Processing Programs (WBS 1.0) Steve Krahn (EM-21) Texas Chee (EM-21) Lead - Jeff Griffin (SRNL) Deputy - Paul Bredt (PNNL) Jay Roach (INL) Ben Lewis (ORNL) Blue - EM-20 Green - SRNL Red - INL Purple - PNNL Brown - ORNL Black - Other Affiliated Institutions Legend: Personnel: Improved Waste Storage

103

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

104

The Defense Waste Processing Facility: Two Years of Radioactive Operation  

Science Conference Proceedings (OSTI)

The Defense Waste Processing Facility (DWPF) at the Savannah River Site in Aiken, SC is currently immobilizing high level radioactive sludge waste in borosilicate glass. The DWPF began vitrification of radioactive waste in May, 1996. Prior to that time, an extensive startup test program was completed with simulated waste. The DWPF is a first of its kind facility. The experience gained and data collected during the startup program and early years of operation can provide valuable information to other similar facilities. This experience involves many areas such as process enhancements, analytical improvements, glass pouring issues, and documentation/data collection and tracking. A summary of this experience and the results of the first two years of operation will be presented.

Marra, S.L. [Westinghouse Savannah River Company, AIKEN, SC (United States); Gee, J.T.; Sproull, J.F.

1998-05-01T23:59:59.000Z

105

Process for remediation of plastic waste - Energy Innovation ...  

A single step process for degrading plastic waste by converting the plastic waste into carbonaceous products via thermal decomposition of the plastic waste by placing ...

106

Waste immobilization demonstration program for the Hanford Site`s Mixed Waste Facility  

Science Conference Proceedings (OSTI)

This paper presents an overview of the Waste Receiving and Processing facility, Module 2A> waste immobilization demonstration program, focusing on the cooperation between Hanford Site, commercial, and international participants. Important highlights of the development and demonstration activities is discussed from the standpoint of findings that have had significant from the standpoint of findings that have had significant impact on the evolution of the facility design. A brief description of the future direction of the program is presented, with emphasis on the key aspects of the technologies that call for further detailed investigation.

Burbank, D.A.; Weingardt, K.M.

1994-05-01T23:59:59.000Z

107

Waste Processing Annual Technology Development Report 2007  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Processing Processing Annual Technology Development Report 2007 SRNS-STI-2008-00040 United States Department of Energy Waste Processing Annual Technology Development Report 2007 Prepared and edited by S. R. Bush EM Technical Integration Office Savannah River National Laboratory Reviewed by Dr. W. R. Wilmarth, Manager EM Technical Integration Office Savannah River National Laboratory Approved by Dr. S. L. Krahn, Director EM-21 Office of Waste Processing U. S. Department of Energy APPROVED for Release for Unlimited (Release to Public) (Signed 08/13/2008) (Signed 08/13/2008) (Signed 08/13/2008) EM-21 Waste Processing Annual Report for Calendar Year 2007 2/74

108

ORISE: Process and Program Evaluation  

NLE Websites -- All DOE Office Websites (Extended Search)

Process and Program Evaluation Process and Program Evaluation As an integral part of producing effective health and safety programs, the Oak Ridge Institute for Science and Education (ORISE) conducts scientific-based process and program evaluation to provide government agencies and organizations with the tools to improve the health of workers and the general public. Whether the goal is to change awareness, attitudes, beliefs, behaviors, policies or systems, ORISE helps determine the right evaluation methods based on specific needs and resources, including: Formative evaluations to assess the problem, target audience needs and guide successful process implementation Assessments to identify unmet needs in programs, organizations or communities Audience evaluations to learn about targeted populations

109

ICPP Waste Management Technology Development Program  

SciTech Connect

As a result of the decision to curtail reprocessing at the Idaho Chemical Processing Plant (ICPP), a Spent fuel and Waste Management Technology Development plan has been implemented to identify acceptable options for disposing of the (1) sodium-bearing liquid radioactive waste, (2) radioactive calcine, and (3) irradiated spent fuel stored at the Idaho National Engineering Laboratory (INEL). The plan was developed jointly by DOE and WINCO.

Hogg, G.W.; Olson, A.L.; Knecht, D.A. [Westinghouse Idaho Nuclear Co., Inc., Idaho Falls, ID (United States); Bonkoski, M.J. [USDOE, Washington, DC (United States)

1993-01-01T23:59:59.000Z

110

Spent Fuel and Waste Management Technology Development Program. Annual progress report  

SciTech Connect

This report provides information on the progress of activities during fiscal year 1993 in the Spent Fuel and Waste Management Technology Development Program (SF&WMTDP) at the Idaho Chemical Processing Plant (ICPP). As a new program, efforts are just getting underway toward addressing major issues related to the fuel and waste stored at the ICPP. The SF&WMTDP has the following principal objectives: Investigate direct dispositioning of spent fuel, striving for one acceptable waste form; determine the best treatment process(es) for liquid and calcine wastes to minimize the volume of high level radioactive waste (HLW) and low level waste (LLW); demonstrate the integrated operability and maintainability of selected treatment and immobilization processes; and assure that implementation of the selected waste treatment process is environmentally acceptable, ensures public and worker safety, and is economically feasible.

Bryant, J.W.

1994-01-01T23:59:59.000Z

111

Emergency Management Program Review at the Waste Isolation Pilot...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Waste Isolation Pilot Plant Emergency Management Program Review at the May 2000 OVERSIGHT Table of Contents EXECUTIVE SUMMARY ......

112

Salt Waste Processing Facility Fact Sheet | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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)

113

High-level waste management technology program plan  

Science Conference Proceedings (OSTI)

The purpose of this plan is to document the integrated technology program plan for the Savannah River Site (SRS) High-Level Waste (HLW) Management System. The mission of the SRS HLW System is to receive and store SRS high-level wastes in a see and environmentally sound, and to convert these wastes into forms suitable for final disposal. These final disposal forms are borosilicate glass to be sent to the Federal Repository, Saltstone grout to be disposed of on site, and treated waste water to be released to the environment via a permitted outfall. Thus, the technology development activities described herein are those activities required to enable successful accomplishment of this mission. The technology program is based on specific needs of the SRS HLW System and organized following the systems engineering level 3 functions. Technology needs for each level 3 function are listed as reference, enhancements, and alternatives. Finally, FY-95 funding, deliverables, and schedules are s in Chapter IV with details on the specific tasks that are funded in FY-95 provided in Appendix A. The information in this report represents the vision of activities as defined at the beginning of the fiscal year. Depending on emergent issues, funding changes, and other factors, programs and milestones may be adjusted during the fiscal year. The FY-95 SRS HLW technology program strongly emphasizes startup support for the Defense Waste Processing Facility and In-Tank Precipitation. Closure of technical issues associated with these operations has been given highest priority. Consequently, efforts on longer term enhancements and alternatives are receiving minimal funding. However, High-Level Waste Management is committed to participation in the national Radioactive Waste Tank Remediation Technology Focus Area. 4 refs., 5 figs., 9 tabs.

Harmon, H.D.

1995-01-01T23:59:59.000Z

114

Rethinking the Hanford Tank Waste Program  

Science Conference Proceedings (OSTI)

The program to treat and dispose of the highly radioactive wastes stored in underground tanks at the U.S. Department of Energy's Hanford site has been studied. A strategy/management approach to achieve an acceptable (technically sound) end state for these wastes has been developed in this study. This approach is based on assessment of the actual risks and costs to the public, workers, and the environment associated with the wastes and storage tanks. Close attention should be given to the technical merits of available waste treatment and stabilization methodologies, and application of realistic risk reduction goals and methodologies to establish appropriate tank farm cleanup milestones. Increased research and development to reduce the mass of non-radioactive materials in the tanks requiring sophisticated treatment is highly desirable. The actual cleanup activities and milestones, while maintaining acceptable safety standards, could be more focused on a risk-to-benefit cost effectiveness, as agreed to by the involved stakeholders and in accordance with existing regulatory requirements. If existing safety standards can be maintained at significant cost savings under alternative plans but with a change in the Tri-Party Agreement (a regulatory requirement), those plans should be carried out. The proposed strategy would also take advantage of the lessons learned from the activities and efforts in the first phase of the two-phased cleanup of the Hanford waste tank farms.

Parker, F. L.; Clark, D. E.; Morcos, N.

2002-02-26T23:59:59.000Z

115

Office of Waste Processing Technical Exchange  

NLE Websites -- All DOE Office Websites (Extended Search)

this hotel at the government per diem rate of 132.00 per night. Please reference the "DOE EM Waste Processing Technical Exchange 2010" when making your reservation to the get...

116

Independent Oversight Review, Oak Ridge Transuranic Waste Processing...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Oak Ridge Transuranic Waste Processing Center, September 2013 September 2013 Review of Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and...

117

Overview of Fiscal Year 2002 Research and Development for Savannah River Site's Salt Waste Processing Facility  

SciTech Connect

The Department of Energy's (DOE) Savannah River Site (SRS) high-level waste program is responsible for storage, treatment, and immobilization of high-level waste for disposal. The Salt Processing Program (SPP) is the salt (soluble) waste treatment portion of the SRS high-level waste effort. The overall SPP encompasses the selection, design, construction and operation of treatment technologies to prepare the salt waste feed material for the site's grout facility (Saltstone) and vitrification facility (Defense Waste Processing Facility). Major constituents that must be removed from the salt waste and sent as feed to Defense Waste Processing Facility include actinides, strontium, cesium, and entrained sludge. In fiscal year 2002 (FY02), research and development (R&D) on the actinide and strontium removal and Caustic-Side Solvent Extraction (CSSX) processes transitioned from technology development for baseline process selection to providing input for conceptual design of the Salt Waste Processing Facility. The SPP R&D focused on advancing the technical maturity, risk reduction, engineering development, and design support for DOE's engineering, procurement, and construction (EPC) contractors for the Salt Waste Processing Facility. Thus, R&D in FY02 addressed the areas of actual waste performance, process chemistry, engineering tests of equipment, and chemical and physical properties relevant to safety. All of the testing, studies, and reports were summarized and provided to the DOE to support the Salt Waste Processing Facility, which began conceptual design in September 2002.

H. D. Harmon, R. Leugemors, PNNL; S. Fink, M. Thompson, D. Walker, WSRC; P. Suggs, W. D. Clark, Jr

2003-02-26T23:59:59.000Z

118

Nuclear Waste Programs semiannual progress report, April--September 1992  

Science Conference Proceedings (OSTI)

This document reports on the work done by the Nuclear Waste Programs of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period April--September 1992. In these programs, studies are underway on the performance of waste glass and spent fuel in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

Bates, J.K.; Bradley, C.R.; Buck, E.C. [and others

1994-05-01T23:59:59.000Z

119

Nuclear waste programs; Semiannual progress report, October 1991--March 1992  

SciTech Connect

This document reports on the work done by the Nuclear Waste Programs of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period October 1991-March 1992. In these programs, studies are underway on the performance of waste glass and spent fuel in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories

Bates, J.K.; Bradley, C.R.; Buck, E.C.; Dietz, N.L.; Ebert, W.L.; Emery, J.W.; Feng, X.; Finn, P.A.; Gerding, T.J.; Hoh, J.C. [and others

1993-11-01T23:59:59.000Z

120

Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program  

SciTech Connect

The Performance Demonstration Program (PDP) for Nondestructive Assay (NDA) is a test program designed to yield data on measurement system capability to characterize drummed transuranic (TRU) waste generated throughout the Department of Energy (DOE) complex. The tests are conducted periodically and provide a mechanism for the independent and objective assessment of NDA system performance and capability relative to the radiological characterization objectives and criteria of the Office of Characterization and Transportation (OCT). The primary documents requiring an NDA PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC), which requires annual characterization facility participation in the PDP, and the Quality Assurance Program Document (QAPD). This NDA PDP implements the general requirements of the QAPD and applicable requirements of the WAC. Measurement facilities must demonstrate acceptable radiological characterization performance through measurement of test samples comprised of pre-specified PDP matrix drum/radioactive source configurations. Measurement facilities are required to analyze the NDA PDP drum samples using the same procedures approved and implemented for routine operational waste characterization activities. The test samples provide an independent means to assess NDA measurement system performance and compliance per criteria delineated in the NDA PDP Plan. General inter-comparison of NDA measurement system performance among DOE measurement facilities and commercial NDA services can also be evaluated using measurement results on similar NDA PDP test samples. A PDP test sample consists of a 55-gallon matrix drum containing a waste matrix type representative of a particular category of the DOE waste inventory and nuclear material standards of known radionuclide and isotopic composition typical of DOE radioactive material. The PDP sample components are made available to participating measurement facilities as designated by the Carlsbad Field Office (CBFO). The nuclear material type, mass and associated alpha activity of the NDA PDP radioactive standard sets have been specified and fabricated to allow assembly of PDP samples that simulate TRU alpha activity concentrations, radionuclidic/isotopic distributions and physical forms typical of the DOE TRU waste inventory. The PDP matrix drum waste matrix types were derived from an evaluation of information contained in the Transuranic Waste Baseline Inventory Report (TWBIR) to ensure representation of prevalent waste types and their associated matrix characteristics in NDA PDP testing. NDA drum analyses required by the Waste Isolation Pilot Plant (WIPP) may only be performed by measurement facilities that comply with the performance criteria as set forth in the NDA PDP Plan. In this document, these analyses are referred to as WIPP analyses, and the wastes on which they are performed are referred to as WIPP wastes.

Carlsbad Field Office

2005-08-03T23:59:59.000Z

Note: This page contains sample records for the topic "waste processing program" 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
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121

Process for treating alkaline wastes for vitrification  

DOE Patents (OSTI)

According to its major aspects and broadly stated, the present invention is a process for treating alkaline waste materials, including high level radioactive wastes, for vitrification. The process involves adjusting the pH of the wastes with nitric acid, adding formic acid (or a process stream containing formic acid) to reduce mercury compounds to elemental mercury and MnO{sub 2} to the Mn(II) ion, and mixing with class formers to produce a melter feed. The process minimizes production of hydrogen due to noble metal-catalyzed formic acid decomposition during, treatment, while producing a redox-balanced feed for effective melter operation and a quality glass product. An important feature of the present invention is the use of different acidifying and reducing, agents to treat the wastes. The nitric acid acidifies the wastes to improve yield stress and supplies acid for various reactions; then the formic acid reduces mercury compounds to elemental mercury and MnO{sub 2}) to the Mn(II) ion. When the pH of the waste is lower, reduction of mercury compounds and MnO{sub 2}) is faster and less formic acid is needed, and the production of hydrogen caused by catalytically-active noble metals is decreased.

Hsu, Chia-lin W.

1994-01-01T23:59:59.000Z

122

Sandia National Laboratories, California Waste Management Program annual report.  

SciTech Connect

The annual program report provides detailed information about all aspects of the Sandia National Laboratories, California (SNL/CA) Waste Management Program. It functions as supporting documentation to the SNL/CA Environmental Management System Program Manual. This annual program report describes the activities undertaken during the past year, and activities planned in future years to implement the Waste Management (WM) Program, one of six programs that supports environmental management at SNL/CA.

Brynildson, Mark E.

2010-02-01T23:59:59.000Z

123

Unit Process Modeling [Nuclear Waste Management using Electrometallurg...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

124

Decontamination processes for waste glass canisters  

SciTech Connect

The process which will be used to decontaminate waste glass canisters at the Savannah River Plant consists of: decontamination (slurry blasting); rinse (high-pressure water); and spot decontamination (high-pressure water plus slurry). No additional waste will be produced by this process because glass frit used in decontamination will be mixed with the radioactive waste and fed into the glass melter. Decontamination of waste glass canisters with chemical and abrasive blasting techniques was investigated. The ability of a chemical technique with HNO/sub 3/-HF and H/sub 2/C/sub 2/O/sub 4/ to remove baked-on contamination was demonstrated. A correlation between oxide removal and decontamination was observed. Oxide removal and, thus, decontamination by abrasive blasting techniques with glass frit as the abrasive was proposed and demonstrated.

Rankin, W.N.

1981-06-01T23:59:59.000Z

125

Exploratory study of complexant concentrate waste processing  

SciTech Connect

The purpose of this exploratory study, conducted by Pacific Northwest Laboratory for Westinghouse Hanford Company, was to determine the effect of applying advanced chemical separations technologies to the processing and disposal of high-level wastes (HLW) stored in underground tanks. The major goals of this study were to determine (1) if the wastes can be partitioned into a small volume of HLW plus a large volume of low-level waste (LLW), and (2) if the activity in the LLW can be lowered enough to meet NRC Class LLW criteria. This report presents the results obtained in a brief scouting study of various processes for separating radionuclides from Hanford complexant concentrate (CC) waste.

Lumetta, G.J.; Bray, L.A.; Kurath, D.E.; Morrey, J.R.; Swanson, J.L.; Wester, D.W.

1993-02-01T23:59:59.000Z

126

Mission Plan for the Civilian Radioactive Waste Management Program |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Mission Plan for the Civilian Radioactive Waste Management Program Mission Plan for the Civilian Radioactive Waste Management Program Mission Plan for the Civilian Radioactive Waste Management Program Summary In response to the the requirement of the Nuclear Waste Policy Act of 1982, the Office of Civilian Radioactive Waste Management in the Department of Energy (DOE) has prepared this Mission Plan for the Civilian Radioactive Waste Management Program. The Mission Plan is divided into two parts. Part I describes the overall goals, objectives, and strategy for the disposal of spent nuclear fuel and high-level waste. It explains that, to meet the directives of the Nuclear Waste Policy Act, the DOE intends to site, design, construct., and start operating a mined geologic repository by January 31, 1998. The Act specifies that the costs of these

127

Los Alamos National Laboratory Transuranic Waste Program Exceeds Planned  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Los Alamos National Laboratory Transuranic Waste Program Exceeds Los Alamos National Laboratory Transuranic Waste Program Exceeds Planned Shipping Goal Los Alamos National Laboratory Transuranic Waste Program Exceeds Planned Shipping Goal May 1, 2012 - 12:00pm Addthis LOS ALAMOS, N.M. - Los Alamos National Laboratory's (LANL) Transuranic (TRU) Waste Program is looking at another record-setting month for the amount of TRU waste leaving Material Disposal Area G, headed to the Waste Isolation Pilot Plant (WIPP) for permanent disposal. LANL exceeded its planned removal of TRU waste from Area G in April, shipping more than 91 cubic meters of waste to WIPP - more than the Lab has ever shipped there in a single month. The Lab is headed for an even more successful May, with 99 cubic meters shipped to WIPP as of May 22. "Our shipping performance reflects the acceleration that began last

128

Experimental program plan for the Waste Isolation Pilot Plant  

SciTech Connect

The US Department of Energy has prepared this Experimental Program Plan for the Waste Isolation Pilot Plant (EPP) to provide a summary of the DOE experimental efforts needed for the performance assessment process for the WIPP, and of the linkages of this process to the appropriate regulations. The Plan encompasses a program of analyses of the performance of the planned repository based on scientific studies, including tests with transuranic waste at laboratory sites, directed at evaluating compliance with the principal regulations governing the WIPP. The Plan begins with background information on the WIPP project, the requirements of the LWA (Land Withdrawal Act), and its objective and scope. It then presents an overview of the regulatory requirements and the compliance approach. Next are comprehensive discussions of plans for compliance with disposal regulations, followed by the SWDA (Solid Waste Disposal Act) and descriptions of activity programs designed to provide information needed for determining compliance. Descriptions and justifications of all currently planned studies designed to support regulatory compliance activities are also included.

Not Available

1994-01-01T23:59:59.000Z

129

Organic Tanks Safety Program: Waste aging studies  

Science Conference Proceedings (OSTI)

The underground storage tanks at the Hanford Complex contain wastes generated from many years of plutonium production and recovery processes, and mixed wastes from radiological degradation processes. The chemical changes of the organic materials used in the extraction processes have a direct on several specific safety issues, including potential energy releases from these tanks. This report details the first year`s findings of a study charged with determining how thermal and radiological processes may change the composition of organic compounds disposed to the tank. Their approach relies on literature precedent, experiments with simulated waste, and studies of model reactions. During the past year, efforts have focused on the global reaction kinetics of a simulated waste exposed to {gamma} radiation, the reactions of organic radicals with nitrite ion, and the decomposition reactions of nitro compounds. In experiments with an organic tank non-radioactive simulant, the authors found that gas production is predominantly radiolytically induced. Concurrent with gas generation they observe the disappearance of EDTA, TBP, DBP and hexone. In the absence of radiolysis, the TBP readily saponifies in the basic medium, but decomposition of the other compounds required radiolysis. Key organic intermediates in the model are C-N bonded compounds such as oximes. As discussed in the report, oximes and nitro compounds decompose in strong base to yield aldehydes, ketones and carboxylic acids (from nitriles). Certain aldehydes can react in the absence of radiolysis to form H{sub 2}. Thus, if the pathways are correct, then organic compounds reacting via these pathways are oxidizing to lower energy content. 75 refs.

Camaioni, D.M.; Samuels, W.D.; Lenihan, B.D.; Clauss, S.A.; Wahl, K.L.; Campbell, J.A.

1994-11-01T23:59:59.000Z

130

Record of Decision for the Solid Waste Program, Hanford Site, Richland, WA: Storage and Treatment of Low-Level Waste and Mixed Low-Level Waste; Disposal of Low-Level Waste and Mixed Low-Level Waste, and Storage, Processing, and Certification of Transuran  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

9 9 Federal Register / Vol. 69, No. 125 / Wednesday, June 30, 2004 / Notices mixed low-level waste, and TRU waste shipments using Year 2000 census data and an updated version of the RADTRAN computer code to calculate potential risks associated with shipping. This analysis included the route- specific impacts of transporting the West Jefferson TRU waste to Hanford and subsequent shipment of this waste to WIPP. Due to the additional TRU waste generated and identified at West Jefferson subsequent to DOE's September 6, 2002, decision, DOE's currently estimated total number of 18 shipments (3 completed RH-TRU waste shipments, 14 remaining RH-TRU waste shipments, and 1 remaining CH-TRU waste shipment) exceeds DOE's prior estimate of total shipments by 3. However, the currently estimated

131

A model for a national low level waste program  

SciTech Connect

A national program for the management of low level waste is essential to the success of environmental clean-up, decontamination and decommissioning, current operations and future missions. The value of a national program is recognized through procedural consistency and a shared set of resources. A national program requires a clear waste definition and an understanding of waste characteristics matched against available and proposed disposal options. A national program requires the development and implementation of standards and procedures for implementing the waste hierarchy, with a specitic emphasis on waste avoidance, minimization and recycling. It requires a common set of objectives for waste characterization based on the disposal facility's waste acceptance criteria, regulatory and license requirements and performance assessments. Finally, a national waste certification program is required to ensure compliance. To facilitate and enhance the national program, a centralized generator services organization, tasked with providing technical services to the generators on behalf of the national program, is necessary. These subject matter experts are the interface between the generating sites and the disposal facility(s). They provide an invaluable service to the generating organizations through their involvement in waste planning prior to waste generation and through championing implementation of the waste hierarchy. Through their interface, national treatment and transportation services are optimized and new business opportunities are identified. This national model is based on extensive experience in the development and on-going management of a national transuranic waste program and management of the national repository, the Waste Isolation Pilot Plant. The Low Level Program at the Savannah River Site also successfully developed and implemented the waste hierarchy, waste certification and waste generator services concepts presented below. The Savannah River Site services over forty generators and has historically managed over 12,000 cubic meters of low level waste annually. The results of the waste minimization program at the site resulted in over 900 initiatives, avoiding over 220,000 cubic meters of waste for a life cycle cost savings of $275 million. At the Los Alamos National Laboratory, the low level waste program services over 20 major generators and several hundred smaller generators that produce over 4,000 cubic meters of low level waste annually. The Los Alamos National Laboratory low level waste program utilizes both on-site and off-site disposal capabilities. Off-site disposal requires the implementation of certification requirements to utilize both federal and commercial options. The Waste Isolation Pilot Plant is the US Department of Energy's first deep geological repository for the permanent disposal of Transuanic waste. Transuranic waste was generated and retrievably stored at 39 sites across the US. Transuranic waste is defined as waste with a radionuclide concentration equal to or greater than 100 nCi/g consisting of radionuclides with half-lives greater than 20 years and with an atomic mass greater than uranium. Combining the lessons learned from the national transuranic waste program, the successful low level waste program at Savannah River Site and the experience of off-site disposal options at Los Alamos National Laboratory provides the framework and basis for developing a viable national strategy for managing low level waste.

Blankenhorn, James A [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

132

UNITED STATES DEPARTMENT OF ENERGY OFFICE OF ENVIRONMENTAL MANAGEMENT WASTE PROCESSING ANNUAL TECHNOLOGY DEVELOPMENT REPORT 2008  

SciTech Connect

The Office of Waste Processing identifies and reduces engineering and technical risks and uncertainties of the waste processing programs and projects of the Department of Energy's Environmental Management (EM) mission through the timely development of solutions to technical issues. The risks, and actions taken to mitigate those risks, are determined through technology readiness assessments, program reviews, technology information exchanges, external technical reviews, technical assistance, and targeted technology development and deployment. The Office of Waste Processing works with other DOE Headquarters offices and project and field organizations to proactively evaluate technical needs, identify multi-site solutions, and improve the technology and engineering associated with project and contract management. Participants in this program are empowered with the authority, resources, and training to implement their defined priorities, roles, and responsibilities. The Office of Waste Processing Multi-Year Program Plan (MYPP) supports the goals and objectives of the U.S. Department of Energy (DOE) - Office of Environmental Management Engineering and Technology Roadmap by providing direction for technology enhancement, development, and demonstration that will lead to a reduction of technical risks and uncertainties in EM waste processing activities. The MYPP summarizes the program areas and the scope of activities within each program area proposed for the next five years to improve safety and reduce costs and environmental impacts associated with waste processing; authorized budget levels will impact how much of the scope of activities can be executed, on a year-to-year basis. Waste Processing Program activities within the Roadmap and the MYPP are described in these seven program areas: (1) Improved Waste Storage Technology; (2) Reliable and Efficient Waste Retrieval Technologies; (3) Enhanced Tank Closure Processes; (4) Next-Generation Pretreatment Solutions; (5) Enhanced Stabilization Technologies; (6) Spent Nuclear Fuel; and (7) Challenging Materials. This report provides updates on 35 technology development tasks conducted during calendar year 2008 in the Roadmap and MYPP program areas.

Bush, S.

2009-11-05T23:59:59.000Z

133

Efficient Separations and Processing Crosscutting Program. Technology summary  

Science Conference Proceedings (OSTI)

The Efficient Separations and Processing (ESP) Crosscutting Program was created in 1991 to identify, develop, and perfect separations technologies and processes to treat wastes and address environmental problems throughout the DOE Complex. The ESP funds several multi-year tasks that address high-priority waste remediation problems involving high-level, low-level, transuranic, hazardous, and mixed (radioactive and hazardous) wastes. The ESP supports applied research and development (R and D) leading to demonstration or use of these separations technologies by other organizations within DOE-EM. Treating essentially all DOE defense wastes requires separation methods that concentrate the contaminants and/or purify waste streams for release to the environment or for downgrading to a waste form less difficult and expensive to dispose of. Initially, ESP R and D efforts focused on treatment of high-level waste (HLW) from underground storage tanks (USTs) because of the potential for large reductions in disposal costs and hazards. As further separations needs emerge and as waste management and environmental restoration priorities change, the program has evolved to encompass the breadth of waste management and environmental remediation problems.

NONE

1995-06-01T23:59:59.000Z

134

Office of Waste Processing Technical Exchange  

NLE Websites -- All DOE Office Websites (Extended Search)

Event Media Links Event Media Links Session 1: Technical Exchange Opening Topic Speaker PDF Podcast S01-01 Welcome T. Michalske, SRNL N/A Podcast S01-03 Introductions G. Flowers, SRNS N/A Podcast S01-04 Opening Remarks I. Triay, DOE-EM Presentation PDF Podcast S01-05 Status of Waste Processing Technology Development S. Schneider, DOE-EM Presentation PDF Podcast S01-06 Hanford/SRS Tank Waste Path Forward K. Subramanian/ T. Sams, SRR/WRPS Presentation PDF Podcast S01-07 Fluidized Bed Steam Reformer Overview B. Mason, TTT Presentation PDF Podcast S01-08 Next Generation Cesium Solvent B.Moyer/S. Fink/M. Geeting, ORNL/SRNL/SRR Presentation PDF Podcast S01-09 Rotary Microfilter Development/Small Column Ion Exchange D. Herman/ R. Edwards, SRNL/SRR Presentation PDF Podcast Session 2: Increased Waste Loading - Improved Current Processing

135

Improved Consolidation Process for Producing Ceramic Waste forms  

DOE Patents (OSTI)

A process for the consolidation and containment of solid or semisolid hazardous waste, which process comprises closing an end of a circular hollow cylinder, filling the cylinder with the hazardous waste, and then cold working the cylinder to reduce its diameter while simultaneously compacting the waste. The open end of the cylinder can be sealed prior to or after the cold working process. The preferred method of cold working is to draw the sealed cylinder containing the hazardous waste through a plurality of dies to simultaneously reduce the diameter of the tube while compacting the waste. This process provides a quick continuous process for consolidating hazardous waste, including radioactive waste.

Hash, Harry C.; Hash, Mark C.

1998-07-24T23:59:59.000Z

136

Systems Engineering in the Development and Implementation of the Savannah River Site Transuranic Waste Disposition Program  

SciTech Connect

The use of systems engineering facilitated the strategic planning and implementation of the Savannah River Site (SRS) transuranic waste disposal program. This application represented the first SRS use of systems engineering in the pre-program planning stages during the development of a comprehensive strategic plan for the disposal of transuranic waste at the Department of Energy Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The use of systems engineering focused the efforts of the technical experts to devise a three initiative plan for the disposal of transuranic waste where previous efforts failed. Continued application of systems engineering facilitated the further development and implementation of the first initiative outlined in the strategic plan, i.e., set-up the program and process to begin to characterize and ship waste to the WIPP.This application of systems engineering to the transuranic waste program represented the first opportunity at the SRS for a comprehensive usage of systems engineering at all program levels. The application was initiated at the earliest possible point in the program development, i.e., strategic planning, and successively was used in detailed development and implementation of the program. Systems engineering successfully focused efforts to produce a comprehensive plan for the disposal of SRS transuranic waste at the WIPP, and facilitated development of the SRS capability and infrastructure to characterize, certify, and ship waste.

Fayfich, R.R.

1999-03-10T23:59:59.000Z

137

Office of Waste Processing Technical Exchange  

NLE Websites -- All DOE Office Websites (Extended Search)

EM Waste Processing Technical Exchange 2010 Agenda EM Waste Processing Technical Exchange 2010 Agenda (Sponsored by EM Office of Waste Processing) November 16 - 18, 2010; Loews Hotel, Atlanta, GA 11/2/2010 Monday, November 15, 2010 5:00 - 7:00 pm Early Registration and Speaker Check-in *Light Refreshments Tuesday Morning, November 16, 2010 Session 1: Technical Exchange Opening (Chair: W. Wilmarth); Salon D Live Webcast Click the video icon to view Session 1 Live Webcast Submit Question Click the Question icon to submit a question. Time Topic Speaker 7:00 am Registration and Check-in 8:00 am S01-01 Welcome T. Michalske, SRNL 8:05 am S01-02 Opening Comments Y. Collazo, DOE-EM 8:15 am S01-03 Introductions G. Flowers, SRNS 8:20 am S01-04 Opening Remarks I. Triay, DOE-EM 8:45 am S01-05 Status of Waste Processing Technology Development

138

Optimizing the National TRU waste system transportation program.  

Science Conference Proceedings (OSTI)

The goal of the National TRU Waste Program (NTP) is to operate the system safely and cost-effectively, in compliance with applicable regulations and agreements, and at full capacity in a fully integrated mode. One of the objectives of the Department of Energy's Carlsbad Field Office (DOE/CBFO) is to complete the current Waste Isolation Pilot Plant (WIPP) mission for the disposal of the nation's legacy transuranic (TRU) waste at least IO years earlier thus saving approximately %7B. The National TRU Waste Optimization Plan (1) recommends changes to accomplish this. This paper discusses the optimization of the National TRU Waste System Transportation Program.

Lott, S. A. (Sheila A.); Countiss, S. (Sue)

2002-01-01T23:59:59.000Z

139

Solid Waste Management Policy and Programs (Minnesota) | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Policy and Programs (Minnesota) Policy and Programs (Minnesota) Solid Waste Management Policy and Programs (Minnesota) < Back Eligibility Utility Fed. Government Commercial Agricultural Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Residential Installer/Contractor Rural Electric Cooperative Tribal Government Low-Income Residential Schools Retail Supplier Institutional Multi-Family Residential Systems Integrator Fuel Distributor Nonprofit General Public/Consumer Transportation Program Info State Minnesota Program Type Siting and Permitting These statutes encourage the State and local governments to develop waste management strategies to achieve the maximum possible reduction in waste generation, eliminate or reduce adverse environmental impacts, encourage

140

Idaho Site Taps Old World Process to Treat Nuclear Waste | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Idaho Site Taps Old World Process to Treat Nuclear Waste Idaho Site Taps Old World Process to Treat Nuclear Waste Idaho Site Taps Old World Process to Treat Nuclear Waste September 9, 2013 - 12:00pm Addthis The Idaho site's sodium distillation system. The Idaho site's sodium distillation system. The top of a sodium distillation vessel, where waste enters the system. The top of a sodium distillation vessel, where waste enters the system. The Idaho site's sodium distillation system. The top of a sodium distillation vessel, where waste enters the system. IDAHO FALLS, Idaho - The EM program at the Idaho site is using an age-old process to treat transuranic (TRU) waste left over from nuclear reactor experiments. Developed in the first century and perfected by moonshiners in the 19th century, distillation will be used at the Idaho Nuclear Technology and

Note: This page contains sample records for the topic "waste processing program" 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

Process for treating alkaline wastes for vitrification  

DOE Patents (OSTI)

A process for treating alkaline wastes for vitrification. The process involves acidifying the wastes with an oxidizing agent such as nitric acid, then adding formic acid as a reducing agent, and then mixing with glass formers to produce a melter feed. The nitric acid contributes nitrates that act as an oxidant to balance the redox of the melter feed, prevent reduction of certain species to produce conducting metals, and lower the pH of the wastes to a suitable level for melter operation. The formic acid reduces mercury compounds to elemental mercury for removal by steam stripping, and MnO.sub.2 to the Mn(II) ion to prevent foaming of the glass melt. The optimum amounts of nitric acid and formic acid are determined in relation to the composition of the wastes, including the concentrations of mercury (II) and MnO.sub.2, noble metal compounds, nitrates, formates and so forth. The process minimizes the amount of hydrogen generated during treatment, while producing a redox-balanced feed for effective melter operation and a quality glass product.

Hsu, Chia-lin W. (Augusta, GA)

1995-01-01T23:59:59.000Z

142

Process and system for treating waste water  

DOE Patents (OSTI)

A process of treating raw or primary waste water using a powdered, activated carbon/aerated biological treatment system is disclosed. Effluent turbidities less than 2 JTU (Jackson turbidity units), zero TOC (total organic carbon) and in the range of 10 mg/l COD (chemical oxygen demand) can be obtained. An influent stream of raw or primary waste water is contacted with an acidified, powdered, activated carbon/alum mixture. Lime is then added to the slurry to raise the pH to about 7.0. A polyelectrolyte flocculant is added to the slurry followed by a flocculation period -- then sedimentation and filtration. The separated solids (sludge) are aerated in a stabilization sludge basin and a portion thereof recycled to an aerated contact basin for mixing with the influent waste water stream prior to or after contact of the influent stream with the powdered, activated carbon/alum mixture.

Olesen, Douglas E. (Kennewick, WA); Shuckrow, Alan J. (Pasco, WA)

1978-01-01T23:59:59.000Z

143

Hazardous Waste Facility Siting Program (Maryland) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Facility Siting Program (Maryland) Facility Siting Program (Maryland) Hazardous Waste Facility Siting Program (Maryland) < Back Eligibility Commercial Construction Industrial Investor-Owned Utility Municipal/Public Utility Retail Supplier Rural Electric Cooperative Transportation Utility Program Info State Maryland Program Type Siting and Permitting Provider Maryland Department of the Environment The Hazardous Waste Facilities Siting Board is responsible for overseeing the siting of hazardous waste facilities in Maryland, and will treat hazardous waste facilities separately from low-level nuclear waste facilities. This legislation describes the factors considered by the Board in making siting decisions. The Board is authorized to enact rules and regulations pertaining to the siting of hazardous and low-level nuclear

144

Federal Energy Management Program: Metering Process  

NLE Websites -- All DOE Office Websites (Extended Search)

Process Process to someone by E-mail Share Federal Energy Management Program: Metering Process on Facebook Tweet about Federal Energy Management Program: Metering Process on Twitter Bookmark Federal Energy Management Program: Metering Process on Google Bookmark Federal Energy Management Program: Metering Process on Delicious Rank Federal Energy Management Program: Metering Process on Digg Find More places to share Federal Energy Management Program: Metering Process on AddThis.com... Sustainable Buildings & Campuses Operations & Maintenance Federal Requirements Program Management Commissioning Metering Systems Approaches Process Computerized Maintenance Management Systems Maintenance Types Major Equipment Types Resources Contacts Greenhouse Gases Water Efficiency Data Center Energy Efficiency

145

Mixed Waste Integrated Program: A technology assessment for mercury-containing mixed wastes  

SciTech Connect

The treatment of mixed wastes must meet US Environmental Protection Agency (EPA) standards for chemically hazardous species and also must provide adequate control of the radioactive species. The US Department of Energy (DOE) Office of Technology Development established the Mixed Waste Integrated Program (MWIP) to develop mixed-waste treatment technology in support of the Mixed Low-Level Waste Program. Many DOE mixed-waste streams contain mercury. This report is an assessment of current state-of-the-art technologies for mercury separations from solids, liquids, and gases. A total of 19 technologies were assessed. This project is funded through the Chemical-Physical Technology Support Group of the MWIP.

Perona, J.J.; Brown, C.H.

1993-03-01T23:59:59.000Z

146

Federal Energy Management Program: Commissioning Process  

NLE Websites -- All DOE Office Websites (Extended Search)

Commissioning Commissioning Process to someone by E-mail Share Federal Energy Management Program: Commissioning Process on Facebook Tweet about Federal Energy Management Program: Commissioning Process on Twitter Bookmark Federal Energy Management Program: Commissioning Process on Google Bookmark Federal Energy Management Program: Commissioning Process on Delicious Rank Federal Energy Management Program: Commissioning Process on Digg Find More places to share Federal Energy Management Program: Commissioning Process on AddThis.com... Sustainable Buildings & Campuses Operations & Maintenance Federal Requirements Program Management Commissioning Types Process Metering Computerized Maintenance Management Systems Maintenance Types Major Equipment Types Resources Contacts Greenhouse Gases

147

Solid Waste Program Fiscal Year 1996 Multi-Year Program Plan WBS 1.2.1, Revision 1  

Science Conference Proceedings (OSTI)

This document contains the Fiscal Year 1996 Multi-Year Program Plan for the Solid Waste Program at the Hanford Reservation in Richland, Washington. The Solid Waste Program treats, stores, and disposes of a wide variety of solid wastes consisting of radioactive, nonradioactive and hazardous material types. Solid waste types are typically classified as transuranic waste, low-level radioactive waste, low-level mixed waste, and non-radioactive hazardous waste. This report describes the mission, goals and program strategies for the Solid Waste Program for fiscal year 1996 and beyond.

NONE

1995-09-01T23:59:59.000Z

148

Evaluating the quality and effectiveness of hazardous waste training programs  

SciTech Connect

An installation`s compliance with Resource Conservation and Recovery Act (RCRA) hazardous waste regulations is strongly dependent on the knowledge, skill, and behavior of all individuals involved in the generation and management of hazardous waste. Recognizing this, Headquarters Air Force Materiel Command (HQ/AFMC) determined that an in-depth evaluation of hazardous waste training programs at each AFMC installation was an appropriate element in assessing the overall effectiveness of installation hazardous waste management programs in preventing noncompliant conditions. Consequently, pursuant to its authority under Air Force Instruction (AFI) 32-7042, Solid and Hazardous Waste Compliance (May 12, 1994) to support and maintain hazardous waste training, HQ/AFMC directed Argonne National Laboratory to undertake the Hazardous Waste Training Initiative. This paper summarizes the methodology employed in performing the evaluation and presents the initiative`s salient conclusions.

Kolpa, R.L.; Haffenden, R.A. [Argonne National Lab., IL (United States); Weaver, M.A. [Headquarters Air Force Materiel Command, Wright-Patterson Air Force Base, OH (United States)

1996-05-01T23:59:59.000Z

149

Waste Form Features, Events, and Processes  

Science Conference Proceedings (OSTI)

The purpose of this report is to evaluate and document the inclusion or exclusion of the waste form features, events and processes (FEPs) with respect to modeling used to support the Total System Performance Assessment for License Application (TSPA-LA). A screening decision, either Included or Excluded, is given for each FEP along with the technical bases for screening decisions. This information is required by the Nuclear Regulatory Commission (NRC) in 10 CFR 63.114 (d, e, and f) [DIRS 156605]. The FEPs addressed in this report deal with the issues related to the degradation and potential failure of the waste form and the migration of the waste form colloids. For included FEPs, this analysis summarizes the implementation of the FEP in TSPA-LA, (i.e., how the FEP is included). For excluded FEPs, this analysis provides the technical bases for exclusion from TSPA-LA (i.e., why the FEP is excluded). This revision addresses the TSPA-LA FEP list (DTN: MO0407SEPFEPLA.000 [DIRS 170760]). The primary purpose of this report is to identify and document the analyses and resolution of the features, events, and processes (FEPs) associated with the waste form performance in the repository. Forty FEPs were identified that are associated with the waste form performance. This report has been prepared to document the screening methodology used in the process of FEP inclusion and exclusion. The analyses documented in this report are for the license application (LA) base case design (BSC 2004 [DIRS 168489]). In this design, a drip shield is placed over the waste package and no backfill is placed over the drip shield (BSC 2004 [DIRS 168489]). Each FEP may include one or more specific issues that are collectively described by a FEP name and a FEP description. The FEP description may encompass a single feature, process or event, or a few closely related or coupled processes if the entire FEP can be addressed by a single specific screening argument or TSPA-LA disposition. The FEPs are addressed in associated analysis or model reports. The assignments were based on the nature of the FEPs so that the analysis and resolution of screening decisions reside with the subject-matter experts in the relevant disciplines.

R. Schreiner

2004-10-27T23:59:59.000Z

150

Civilian radioactive waste management program plan. Revision 2  

SciTech Connect

This revision of the Civilian Radioactive Waste Management Program Plan describes the objectives of the Civilian Radioactive Waste management Program (Program) as prescribed by legislative mandate, and the technical achievements, schedule, and costs planned to complete these objectives. The Plan provides Program participants and stakeholders with an updated description of Program activities and milestones for fiscal years (FY) 1998 to 2003. It describes the steps the Program will undertake to provide a viability assessment of the Yucca Mountain site in 1998; prepare the Secretary of Energy`s site recommendation to the President in 2001, if the site is found to be suitable for development as a repository; and submit a license application to the Nuclear Regulatory Commission in 2002 for authorization to construct a repository. The Program`s ultimate challenge is to provide adequate assurance to society that an operating geologic repository at a specific site meets the required standards of safety. Chapter 1 describes the Program`s mission and vision, and summarizes the Program`s broad strategic objectives. Chapter 2 describes the Program`s approach to transform strategic objectives, strategies, and success measures to specific Program activities and milestones. Chapter 3 describes the activities and milestones currently projected by the Program for the next five years for the Yucca Mountain Site Characterization Project; the Waste Acceptance, Storage and Transportation Project; ad the Program Management Center. The appendices present information on the Nuclear Waste Policy Act of 1982, as amended, and the Energy Policy Act of 1992; the history of the Program; the Program`s organization chart; the Commission`s regulations, Disposal of High-Level Radioactive Wastes in geologic Repositories; and a glossary of terms.

1998-07-01T23:59:59.000Z

151

Process Design Concepts for Stabilization of High Level Waste Calcine  

Science Conference Proceedings (OSTI)

The current baseline assumption is that packaging ˇ§as isˇ¨ and direct disposal of high level waste (HLW) calcine in a Monitored Geologic Repository will be allowed. The fall back position is to develop a stabilized waste form for the HLW calcine, that will meet repository waste acceptance criteria currently in place, in case regulatory initiatives are unsuccessful. A decision between direct disposal or a stabilization alternative is anticipated by June 2006. The purposes of this Engineering Design File (EDF) are to provide a pre-conceptual design on three low temperature processes under development for stabilization of high level waste calcine (i.e., the grout, hydroceramic grout, and iron phosphate ceramic processes) and to support a down selection among the three candidates. The key assumptions for the pre-conceptual design assessment are that a) a waste treatment plant would operate over eight years for 200 days a year, b) a design processing rate of 3.67 m3/day or 4670 kg/day of HLW calcine would be needed, and c) the performance of waste form would remove the HLW calcine from the hazardous waste category, and d) the waste form loadings would range from about 21-25 wt% calcine. The conclusions of this EDF study are that: (a) To date, the grout formulation appears to be the best candidate stabilizer among the three being tested for HLW calcine and appears to be the easiest to mix, pour, and cure. (b) Only minor differences would exist between the process steps of the grout and hydroceramic grout stabilization processes. If temperature control of the mixer at about 80„aC is required, it would add a major level of complexity to the iron phosphate stabilization process. (c) It is too early in the development program to determine which stabilizer will produce the minimum amount of stabilized waste form for the entire HLW inventory, but the volume is assumed to be within the range of 12,250 to 14,470 m3. (d) The stacked vessel height of the hot process vessels in the hydroceramic grout process (i.e., 21 m) appears to be about the same as that estimated by the Direct Cementitious Waste Process in 1998, for which a conceptual design was developed. Some of the conceptual design efforts in the 1998 study may be applicable to the stabilizer processes addressed in this EDF. (e) The gamma radiation fields near the process vessels handling HLW calcine would vary from a range of about 300-350 R/hr at a distance of 2.5 cm from the side of the vessels to a range of about 50-170 R/hr at a distance of 100 cm from the side of the vessels. The calculations were made for combined calcine, which was defined as the total HLW calcine inventory uniformly mixed. (f) The gamma radiation fields near the stabilized waste in canisters would range from about 25-170 R/hr at 2.5 cm from the side of the canister and 5-35 R/hr at 100 cm from the side of the canister, depending on the which bin set was the source of calcine.

T. R. Thomas; A. K. Herbst

2005-06-01T23:59:59.000Z

152

Office of Waste Processing Technical Exchange  

NLE Websites -- All DOE Office Websites (Extended Search)

Agenda Hotel Register Contacts Event Media Speaker Information Home Agenda Hotel Register Contacts Event Media Speaker Information Home Environmental Management Waste Processing Technical Exchange 2010 in Atlanta, GA, November 16 - 18. Over the past eight years, personnel from the three sites, Savannah River/Hanford/Idaho along with others receiving funding from the Environmental Management Office of Waste Processing have met to exchange recent results of on-going field operations and technology development. The purpose of this exchange is to provide a forum for discussion of each Site's efforts to accelerate cleanup operations. Keys to success and lessons learned are openly exchanged in a manner to allow for open discussion between operations, engineering and scientists to accelerate transition of technologies from concepts to field implementation.

153

Modified Bayer Process for Alumina Removal from Hanford Waste  

AREVA NC Inc. Modified Bayer Process for Alumina Removal from Hanford Waste January 24, 2007 Don Geniesse AREVA NC Inc.

154

TRU Waste Sampling Program: Volume II. Gas generation studies  

DOE Green Energy (OSTI)

Volume II of the TRU Waste Sampling Program report contains the data generated from evaluating the adequacy of venting/filtering devices for maintaining safe hydrogen levels in plutonium contaminated waste drums. Additional studies reported in this volume include gas generation rates, selected waste form monitoring, and evaluation of hydrogen migration from sealed 90-mil rigid polyethylene drum liners containing /sup 238/Pu-contaminated wastes. All wastes used in the studies were newly-generated, and the waste drums were under controlled, experimental conditions. Studies using /sup 239/Pu-contaminated wastes were conducted at the Rocky Flats Plant. Studies using /sup 238/Pu-contaminated wastes were conducted at the Los Alamos National Laboratory.

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

1985-09-01T23:59:59.000Z

155

Quality assurance program description: Hanford Waste Vitrification Plant, Part 1. Revision 3  

SciTech Connect

This document describes the Department of Energy`s Richland Field Office (DOE-RL) quality assurance (QA) program for the processing of high-level waste as well as the Vitrification Project Quality Assurance Program for the design and construction of the Hanford Waste Vitrification Plant (HWVP). It also identifies and describes the planned activities that constitute the required quality assurance program for the HWVP. This program applies to the broad scope of quality-affecting activities associated with the overall HWVP Facility. Quality-affecting activities include designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, maintaining, repairing, and modifying. Also included are the development, qualification, and production of waste forms which may be safely used to dispose of high-level radioactive waste resulting from national defense activities. The HWVP QA program is made up of many constituent programs that are being implemented by the participating organizations. This Quality Assurance program description is intended to outline and define the scope and application of the major programs that make up the HWVP QA program. It provides a means by which the overall program can be managed and directed to achieve its objectives. Subsequent parts of this description will identify the program`s objectives, its scope, application, and structure.

Not Available

1992-12-31T23:59:59.000Z

156

Federal Energy Management Program: Product Designation Process  

NLE Websites -- All DOE Office Websites (Extended Search)

Product Product Designation Process to someone by E-mail Share Federal Energy Management Program: Product Designation Process on Facebook Tweet about Federal Energy Management Program: Product Designation Process on Twitter Bookmark Federal Energy Management Program: Product Designation Process on Google Bookmark Federal Energy Management Program: Product Designation Process on Delicious Rank Federal Energy Management Program: Product Designation Process on Digg Find More places to share Federal Energy Management Program: Product Designation Process on AddThis.com... Energy-Efficient Products Federal Requirements Covered Product Categories Product Designation Process Low Standby Power Energy & Cost Savings Calculators Model Acquisitions Language Working Group Resources

157

Process Waste Assessment for the Diana Laser Laboratory  

SciTech Connect

This Process Waste Assessment was conducted to evaluate the Diana Laser Laboratory, located in the Combustion Research Facility. It documents the hazardous chemical waste streams generated by the laser process and establishes a baseline for future waste minimization efforts. This Process Waste Assessment will be reevaluated in approximately 18 to 24 months, after enough time has passed to implement recommendations and to compare results with the baseline established in this assessment.

Phillips, N.M.

1993-12-01T23:59:59.000Z

158

DOE Seeks Independent Evaluation of Remote-Handled Waste Program  

NLE Websites -- All DOE Office Websites (Extended Search)

Seeks Independent Evaluation Seeks Independent Evaluation Of Remote-Handled Waste Program CARLSBAD, N.M., July 24, 2001 - An independent panel of scientific and engineering experts will convene July 30 in Carlsbad to evaluate U.S. Department of Energy (DOE) plans for managing remote-handled (RH) transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP). DOE's Carlsbad Field Office has asked the American Society of Mechanical Engineers and the Institute for Regulatory Science to review its proposed RH-TRU waste program. The program must be approved by the New Mexico Environment Department and the U.S. Environmental Protection Agency before DOE will be permitted to accept and dispose of RH-TRU waste at WIPP. "Safety and compliance are our primary considerations in developing the plans for

159

Proceedings of the 17th Biennial Waste Processing Conference WASTE SEPARATION-  

E-Print Network (OSTI)

Proceedings of the 17th Biennial Waste Processing Conference ASME 1996 WASTE SEPARATION- DOES IT INFLUENCE MUNICIPAL WASTE COMBUSTOR EMISSIONS? A. John Chandler A.J. Chandler & Associates Ltd. Willowdale that MSW incinerator emissions show significant variations because of the heterogeneous nature of the waste

Columbia University

160

Fiscal year 1986 program plan for the Defense Transuranic Waste Program (DTWP)  

SciTech Connect

The Defense TRU Waste Program (DTWP) is the focal point for the Department of Energy is national planning, integration, and technical development for TRU waste management. The scope of this program extends from the point of TRU waste generation through delivery to a permanent repository. The TRU program maintains a close interface with repository development to ensure program compatibility and coordination. The defense TRU program does not directly address commercial activities that generate TRU waste. Instead, it is concerned with providing alternatives to manage existing and future defense TRU wastes. The FY 86 Program Plan is consistent with the Defense TRU Waste Program goals and objectives stated in the Defense Transuranic Waste Program Strategy Document, January 1984. The roles of participants, the responsibilities and authorities for Research Development (R D), the organizational interfaces and communication channels for R D and the establishment of procedures for planning, reporting, and budgeting of all R D activities meet requirements tated in the Technical Management Plan for the Transuranic Waste Management Program. The Program Plan is revised as needed. Detailed budget planning (i.e., programmatic funding and capital equipment) is presented for FY 86; outyear budget projections are presented for future years.

1985-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste processing program" from the National Library of EnergyBeta (NLEBeta).
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161

Facility design philosophy: Tank Waste Remediation System Process support and infrastructure definition  

Science Conference Proceedings (OSTI)

This report documents the current facility design philosophy for the Tank Waste Remediation System (TWRS) process support and infrastructure definition. The Tank Waste Remediation System Facility Configuration Study (FCS) initially documented the identification and definition of support functions and infrastructure essential to the TWRS processing mission. Since the issuance of the FCS, the Westinghouse Hanford Company (WHC) has proceeded to develop information and requirements essential for the technical definition of the TWRS treatment processing programs.

Leach, C.E.; Galbraith, J.D. [Westinghouse Hanford Co., Richland, WA (United States); Grant, P.R.; Francuz, D.J.; Schroeder, P.J. [Fluor Daniel, Inc., Richland, WA (United States)

1995-11-01T23:59:59.000Z

162

Mixed Waste Integrated Program Quality Assurance requirements plan  

SciTech Connect

Mixed Waste Integrated Program (MWIP) is sponsored by the US Department of Energy (DOE), Office of Technology Development, Waste Management Division. The strategic objectives of MWIP are defined in the Mixed Waste Integrated Program Strategic Plan, and expanded upon in the MWIP Program Management Plan. This MWIP Quality Assurance Requirement Plan (QARP) applies to mixed waste treatment technologies involving both hazardous and radioactive constituents. As a DOE organization, MWIP is required to develop, implement, and maintain a written Quality Assurance Program in accordance with DOE Order 4700.1 Project Management System, DOE Order 5700.6C, Quality Assurance, DOE Order 5820.2A Radioactive Waste Management, ASME NQA-1 Quality Assurance Program Requirements for Nuclear Facilities and ANSI/ASQC E4-19xx Specifications and Guidelines for Quality Systems for Environmental Data Collection and Environmental Technology Programs. The purpose of the MWIP QA program is to establish controls which address the requirements in 5700.6C, with the intent to minimize risks and potential environmental impacts; and to maximize environmental protection, health, safety, reliability, and performance in all program activities. QA program controls are established to assure that each participating organization conducts its activities in a manner consistent with risks posed by those activities.

1994-04-15T23:59:59.000Z

163

Savannah River Site Marks Waste Processing Milestone with Melter's  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Marks Waste Processing Milestone with Marks Waste Processing Milestone with Melter's 2,000th Waste Canister Savannah River Site Marks Waste Processing Milestone with Melter's 2,000th Waste Canister February 1, 2012 - 12:00pm Addthis A Savannah River Remediation employee uses a manipulator located inside a shielded enclosure at the Defense Waste Processing Facility, where a melter pours molten glass into a canister. A Savannah River Remediation employee uses a manipulator located inside a shielded enclosure at the Defense Waste Processing Facility, where a melter pours molten glass into a canister. AIKEN, S.C. - The second melter to operate in the 16-year history of the nation's largest radioactive waste glassification plant shows no signs of slowing after recently pouring its 2,000 canister of glass-formed hazardous

164

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

165

Savannah River Site Marks Waste Processing Milestone with Melter's  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Savannah River Site Marks Waste Processing Milestone with Savannah River Site Marks Waste Processing Milestone with Melter's 2,000th Waste Canister Savannah River Site Marks Waste Processing Milestone with Melter's 2,000th Waste Canister February 1, 2012 - 12:00pm Addthis A Savannah River Remediation employee uses a manipulator located inside a shielded enclosure at the Defense Waste Processing Facility, where a melter pours molten glass into a canister. A Savannah River Remediation employee uses a manipulator located inside a shielded enclosure at the Defense Waste Processing Facility, where a melter pours molten glass into a canister. AIKEN, S.C. - The second melter to operate in the 16-year history of the nation's largest radioactive waste glassification plant shows no signs of slowing after recently pouring its 2,000 canister of glass-formed hazardous

166

Materials and Processes to Immobilize Nuclear Waste  

Science Conference Proceedings (OSTI)

Oct 8, 2012 ... While borosilicate glass is widely regarded as baseline technology for nuclear waste immobilisation, there are a wide range of such wastes that ...

167

Design of waste tyre pyrolysis process.  

E-Print Network (OSTI)

??xviii, 164 p. : ill. (some col.) ; 30 cm HKUST Call Number: Thesis CBME 2009 LeeK Waste tyre, one kind of non-biodegradable solid wastes,… (more)

Lee, King Lung

2009-01-01T23:59:59.000Z

168

Savannah River Site - Salt Waste Processing Facility: Briefing on the Salt Waste Processing Facility Independent Technical Review  

Energy.gov (U.S. Department of Energy (DOE))

This is a presentation outlining the Salt Waste Processing Facility process, major risks, approach for conducting reviews, discussion of the findings, and conclusions.

169

Double Shell Tank (DST) Process Waste Sampling Subsystem Specification  

SciTech Connect

This specification establishes the performance requirements and provides references to the requisite codes and standards to be applied to the Double-Shell Tank (DST) Process Waste Sampling Subsystem which supports the first phase of Waste Feed Delivery.

RASMUSSEN, J.H.

2000-05-03T23:59:59.000Z

170

GEOTECHNICAL/GEOCHEMICAL CHARACTERIZATION OF ADVANCED COAL PROCESS WASTE STREAMS  

Science Conference Proceedings (OSTI)

Thirteen solid wastes, six coals and one unreacted sorbent produced from seven advanced coal utilization processes were characterized for task three of this project. The advanced processes from which samples were obtained included a gas-reburning sorbent injection process, a pressurized fluidized-bed coal combustion process, a coal-reburning process, a SO{sub x}, NO{sub x}, RO{sub x}, BOX process, an advanced flue desulfurization process, and an advanced coal cleaning process. The waste samples ranged from coarse materials, such as bottom ashes and spent bed materials, to fine materials such as fly ashes and cyclone ashes. Based on the results of the waste characterizations, an analysis of appropriate waste management practices for the advanced process wastes was done. The analysis indicated that using conventional waste management technology should be possible for disposal of all the advanced process wastes studied for task three. However, some wastes did possess properties that could present special problems for conventional waste management systems. Several task three wastes were self-hardening materials and one was self-heating. Self-hardening is caused by cementitious and pozzolanic reactions that occur when water is added to the waste. All of the self-hardening wastes setup slowly (in a matter of hours or days rather than minutes). Thus these wastes can still be handled with conventional management systems if care is taken not to allow them to setup in storage bins or transport vehicles. Waste self-heating is caused by the exothermic hydration of lime when the waste is mixed with conditioning water. If enough lime is present, the temperature of the waste will rise until steam is produced. It is recommended that self-heating wastes be conditioned in a controlled manner so that the heat will be safely dissipated before the material is transported to an ultimate disposal site. Waste utilization is important because an advanced process waste will not require ultimate disposal when it is put to use. Each task three waste was evaluated for utilization potential based on its physical properties, bulk chemical composition, and mineral composition. Only one of the thirteen materials studied might be suitable for use as a pozzolanic concrete additive. However, many wastes appeared to be suitable for other high-volume uses such as blasting grit, fine aggregate for asphalt concrete, road deicer, structural fill material, soil stabilization additives, waste stabilization additives, landfill cover material, and pavement base course construction.

Edwin S. Olson; Charles J. Moretti

1999-11-01T23:59:59.000Z

171

Hanford Site waste tank farm facilities design reconstitution program plan  

SciTech Connect

Throughout the commercial nuclear industry the lack of design reconstitution programs prior to the mid 1980`s has resulted in inadequate documentation to support operating facilities configuration changes or safety evaluations. As a result, many utilities have completed or have ongoing design reconstitution programs and have discovered that without sufficient pre-planning their program can be potentially very expensive and may result in end-products inconsistent with the facility needs or expectations. A design reconstitution program plan is developed here for the Hanford waste tank farms facility as a consequence of the DOE Standard on operational configuration management. This design reconstitution plan provides for the recovery or regeneration of design requirements and basis, the compilation of Design Information Summaries, and a methodology to disposition items open for regeneration that were discovered during the development of Design Information Summaries. Implementation of this plan will culminate in an end-product of about 30 Design Information Summary documents. These documents will be developed to identify tank farms facility design requirements and design bases and thereby capture the technical baselines of the facility. This plan identifies the methodology necessary to systematically recover documents that are sources of design input information, and to evaluate and disposition open items or regeneration items discovered during the development of the Design Information Summaries or during the verification and validation processes. These development activities will be governed and implemented by three procedures and a guide that are to be developed as an outgrowth of this plan.

Vollert, F.R.

1994-09-06T23:59:59.000Z

172

Scenarios of the TWRS low-level waste disposal program  

Science Conference Proceedings (OSTI)

As a result of past Department of Energy (DOE) weapons material production operations, Hanford now stores nuclear waste from processing facilities in underground tanks on the 200 Area plateau. An agreement between the DOE, the Environmental Protection Agency (EPA), and the Washington state Department of Ecology (the Tri-Party Agreement, or TPA) establishes an enforceable schedule and a technical framework for recovering, processing, solidifying, and disposing of the Hanford tank wastes. The present plan includes retrieving the tank waste, pretreating the waste to separate into low level and high level streams, and converting both streams to a glass waste form. The low level glass will represent by far the largest volume and lowest quantity of radioactivity (i.e., large volume of waste chemicals) of waste requiring disposal. The low level glass waste will be retrievably stored in sub-surface disposal vaults for several decades. If the low level disposal system proves to be acceptable, the disposal site will be closed with the low level waste in place. If, however, at some time the disposal system is found to be unacceptable, then the waste can be retrieved and dealt with in some other manner. WHC is planning to emplace the waste so that it is retrievable for up to 50 years after completion of the tank waste processing. Acceptability of disposal of the TWRS low level waste at Hanford depends on technical, cultural, and political considerations. The Performance Assessment is a major part of determining whether the proposed disposal action is technically defensible. A Performance Assessment estimates the possible future impact to humans and the environment for thousands of years into the future. In accordance with the TPA technical strategy, WHC plans to design a near-surface facility suitable for disposal of the glass waste.

NONE

1994-10-01T23:59:59.000Z

173

Construction Begins on New Waste Processing Facility | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Construction Begins on New Waste Processing Facility Construction Begins on New Waste Processing Facility Construction Begins on New Waste Processing Facility February 9, 2012 - 12:00pm Addthis Workers construct a new facility that will help Los Alamos National Laboratory accelerate the shipment of transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad for permanent disposal. Workers construct a new facility that will help Los Alamos National Laboratory accelerate the shipment of transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad for permanent disposal. Construction has begun on a new facility that will help Los Alamos National Laboratory accelerate the shipment of transuranic (TRU) waste stored in large boxes at Technical Area 54, Area G. Construction has begun on a new facility that will help Los Alamos National

174

Waste Treatment Plant and Tank Farm Program  

Energy.gov (U.S. Department of Energy (DOE))

This photo shows the Pretreatment Facility control room building pad at the Office of River Protection at the Hanford site. The Low-Activity Waste Facility is in the background.

175

SRS Liquid Waste Program Partnering Agreement  

Energy.gov (U.S. Department of Energy (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...

176

Independent Oversight Assessment, Salt Waste Processing Facility Project -  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Salt Waste Processing Facility Salt Waste Processing Facility Project - January 2013 Independent Oversight Assessment, Salt Waste Processing Facility Project - January 2013 January 2013 Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project The U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), conducted an independent assessment of nuclear safety culture at the Salt Waste Processing Facility (SWPF) Project. The primary objective of the evaluation was to provide information regarding the status of the safety culture at the SWPF Project. The data collection phase of the assessment occurred during August - September 2012. Independent Oversight Assessment, Salt Waste Processing Facility Project -

177

Hydrothermal processing of Hanford tank wastes: Process modeling and control  

Science Conference Proceedings (OSTI)

In the Los Alamos National Laboratory (LANL) hydrothermal process, waste streams are first pressurized and heated as they pass through a continuous flow tubular reactor vessel. The waste is maintained at reaction temperature of 300--550 C where organic destruction and sludge reformation occur. This report documents LANL activities in process modeling and control undertaken in FY94 to support hydrothermal process development. Key issues discussed include non-ideal flow patterns (e.g. axial dispersion) and their effect on reactor performance, the use and interpretation of inert tracer experiments, and the use of computational fluid mechanics to evaluate novel hydrothermal reactor designs. In addition, the effects of axial dispersion (and simplifications to rate expressions) on the estimated kinetic parameters are explored by non-linear regression to experimental data. Safety-related calculations are reported which estimate the explosion limits of effluent gases and the fate of hydrogen as it passes through the reactor. Development and numerical solution of a generalized one-dimensional mathematical model is also summarized. The difficulties encountered in using commercially available software to correlate the behavior of high temperature, high pressure aqueous electrolyte mixtures are summarized. Finally, details of the control system and experiments conducted to empirically determine the system response are reported.

Currier, R.P. [comp.

1994-10-01T23:59:59.000Z

178

Salt Waste Processing Facility Fact Sheet  

Energy.gov (U.S. Department of Energy (DOE))

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.

179

Process for treating fission waste. [Patent application  

DOE Patents (OSTI)

A method is described for the treatment of fission waste. A glass forming agent, a metal oxide, and a reducing agent are mixed with the fission waste and the mixture is heated. After melting, the mixture separates into a glass phase and a metal phase. The glass phase may be used to safely store the fission waste, while the metal phase contains noble metals recovered from the fission waste.

Rohrmann, C.A.; Wick, O.J.

1981-11-17T23:59:59.000Z

180

Melt-processed Multiphasic Ceramic Waste Forms  

Science Conference Proceedings (OSTI)

Symposium, Materials Issues in Nuclear Waste Management in the 21st Century ... Scanning electron microscopy (SEM) and energy dispersive spectrometry ...

Note: This page contains sample records for the topic "waste processing program" 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

Characterization of industrial process waste heat and input heat streams  

SciTech Connect

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

182

Review of the Savannah River Site Salt Waste Processing Facility...  

NLE Websites -- All DOE Office Websites (Extended Search)

River Site Salt Waste Processing Facility Safety Basis and Design Development May 2011 August 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement...

183

Waste Heat Recovery from Industrial Process Heating Equipment...  

NLE Websites -- All DOE Office Websites (Extended Search)

Waste Heat Recovery from Industrial Process Heating Equipment - Cross-cutting Research and Development Priorities Speaker(s): Sachin Nimbalkar Date: January 17, 2013 - 11:00am...

184

Process Chemistry and Operations Planning for Hanford Waste ...  

Process Chemistry and Operations Planning for Hanford Waste Alternatives L. T. Smith,* R. K. Toghiani, and J. S. Lindner Institute for Clean Energy Technology (ICET ...

185

Newly Generated Liquid Waste Processing Alternatives Study, Volume 1  

SciTech Connect

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

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

2002-09-01T23:59:59.000Z

186

Fuzzy parametric programming model for multi-objective integrated solid waste management under uncertainty  

Science Conference Proceedings (OSTI)

Solid waste management is increasingly becoming a challenging task for the municipal authorities due to increasing waste quantities, changing waste composition, decreasing land availability for waste disposal sites and increasing awareness about the ... Keywords: Fuzzy parametric programming, Integrated solid waste management system, Long term planning, Multi-objective and multi-period planning, Solid waste management

Amitabh Kumar Srivastava; Arvind K. Nema

2012-04-01T23:59:59.000Z

187

Thermocatalytic conversion of food processing wastes: Topical report, FY 1988  

DOE Green Energy (OSTI)

The efficient utilization of waste produced during food processing operations is a topic of growing importance to the industry. While incineration is an attractive option for wastes with relatively low ash and moisture contents (i.e., under about 50 wt % moisture), it is not suitable for wastes with high moisture contents. Cheese whey, brewer's spent grain, and fruit pomace are examples of food processing wastes that are generally too wet to burn efficiently and cleanly. Pacific Northwest Laboratory (PNL) is developing a thermocatalytic conversion process that can convert high-moisture wastes (up to 98 wt % moisture) to a medium-Btu fuel gas consisting primarily of methane and carbon dioxide. At the same time, the COD of these waste streams is reduced by 90% to 99%, Organic wastes are converted by thermocatalytic treatment at 350/degree/C to 400/degree/C and 3000 to 4000 psig. The process offers a relatively simple solution to waste treatment while providing net energy production from wastes containing as little as 2 wt % organic solids (this is equivalent to a COD of approximately 25,000 mg/L). This report describes continuous reactor system (CRS) experiments that have been conducted with food processing wastes. The purpose of the CRS experiments was to provide kinetic and catalyst lifetime data, which could not be obtained with the batch reactor tests. These data are needed for commercial scaleup of the process.

Baker, E.G.; Butner, R.S.; Sealock, L.J. Jr.; Elliott, D.C.; Neuenschwander, G.G.

1989-01-01T23:59:59.000Z

188

Waste management/waste certification plan for the Oak Ridge National Laboratory Environmental Restoration Program  

Science Conference Proceedings (OSTI)

This Waste Management/Waste Certification (C) Plan, written for the Environmental Restoration (ER) Program at Oak Ridge National Laboratory (ORNL), outlines the criteria and methodologies to be used in the management of waste generated during ORNL ER field activities. Other agreed upon methods may be used in the management of waste with consultation with ER and Waste Management Organization. The intent of this plan is to provide information for the minimization, handling, and disposal of waste generated by ER activities. This plan contains provisions for the safe and effective management of waste consistent with the U.S. Environmental Protection Agency`s (EPA`s) guidance. Components of this plan have been designed to protect the environment and the health and safety of workers and the public. It, therefore, stresses that investigation derived waste (IDW) and other waste be managed to ensure that (1) all efforts be made to minimize the amount of waste generated; (2) costs associated with sampling storage, analysis, transportation, and disposal are minimized; (3) the potential for public and worker exposure is not increased; and (4) additional contaminated areas are not created.

Clark, C. Jr.; Hunt-Davenport, L.D.; Cofer, G.H.

1995-03-01T23:59:59.000Z

189

Transuranic Solid Waste Management Programs. Progress report, July-- December 1974  

SciTech Connect

Progress is reported for three transuranic solid waste management programs funded at the Los Alamos Scientific Laboratory by the Energy Research and Development Administration Division of Waste Management and Transportation. Under the Transuranic Waste Research and Development Program, a completed evaluation of stainless steel drums showed that although the material has superior corrosion-resistant properties, its higher cost makes a thorough investigation of other container systems mandatory. A program to investigate more economical, nonmetallic containers is proposed. Preliminary fire tests in mild steel drums have been completed with fire propagation not appearing to be a problem unless container integrity is lost. Investigation of the corrosion of mild steel drums and the evaluation of potential corrosion inhibitors, in a variety of humid environments, continues. Experimental results of both laboratory and field investigations on radiolysis of transuranic elements in hydrogenous waste are discussed. Progress in the development of instrumentation for monitoring and segregating low-level wastes is described. New plans and developments for the Transuranic-Contaminated Solid Waste Treatment Development Facility are presented. The current focus is on a comparison of all alternative waste reduction systems toward a relative Figure of Merit with universal application. Drawings, flowsheets, and building layouts are included, and the proposed incinerator device is detailed. The release mechanisms, inter- and intraregional transport mechanisms, and exhumation studies relevant to the Evaluation of Transuranic-Contaminated Radioactive Waste Disposal Areas Program are defined and analyzed. A detailed description is given of the formulation of the computer simulation scheme for the intraregional biological transport model. (auth)

1975-10-01T23:59:59.000Z

190

Application to ship nonmixed transuranic waste to the Nevada Test Site for interim storage. Waste Cerification Program  

SciTech Connect

This report documents various regulations on radioactive waste processing and discusses how the Waste Isolation Pilot Plant will comply with and meet these requirements. Specific procedures are discussed concerning transuranic, metal scrap, salt block, solid, and glove box wastes.

Not Available

1993-12-01T23:59:59.000Z

191

Mixed Waste Advanced Treatment Technology: Waste Processing Products and Their Recycling Applications  

Science Conference Proceedings (OSTI)

During their operations, nuclear power plants generate mixed waste containing both hazardous and radioactive constituents. Disposal options for such mixed waste are limited and expensive. EPRI research has demonstrated that an innovative molten metal process for destroying hazardous wastes can be used effectively on nuclear power plant wastes containing both hazardous and radioactive constituents. Preliminary results of this research indicate that the destruction of the hazardous constituents is complete...

1997-12-31T23:59:59.000Z

192

Data Quality Objectives for Tank Farms Waste Compatibility Program  

SciTech Connect

There are 177 waste storage tanks containing over 210,000 m{sup 3} (55 million gal) of mixed waste at the Hanford Site. The River Protection Project (RPP) has adopted the data quality objective (DQO) process used by the U.S. Environmental Protection Agency (EPA) (EPA 1994a) and implemented by RPP internal procedure (Banning 1999a) to identify the information and data needed to address safety issues. This DQO document is based on several documents that provide the technical basis for inputs and decision/action levels used to develop the decision rules that evaluate the transfer of wastes. A number of these documents are presently in the process of being revised. This document will need to be revised if there are changes to the technical criteria in these supporting documents. This DQO process supports various documents, such as sampling and analysis plans and double-shell tank (DST) waste analysis plans. This document identifies the type, quality, and quantity of data needed to determine whether transfer of supernatant can be performed safely. The requirements in this document are designed to prevent the mixing of incompatible waste as defined in Washington Administrative Code (WAC) 173-303-040. Waste transfers which meet the requirements contained in this document and the Double-Shell Tank Waste Analysis Plan (Mulkey 1998) are considered to be compatible, and prevent the mixing of incompatible waste.

BANNING, D.L.

1999-07-02T23:59:59.000Z

193

Thermal processing system concepts and considerations for RWMC buried waste  

SciTech Connect

This report presents a preliminary determination of ex situ thermal processing system concepts and related processing considerations for application to remediation of transuranic (TRU)-contaminated buried wastes (TRUW) at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL). Beginning with top-level thermal treatment concepts and requirements identified in a previous Preliminary Systems Design Study (SDS), a more detailed consideration of the waste materials thermal processing problem is provided. Anticipated waste stream elements and problem characteristics are identified and considered. Final waste form performance criteria, requirements, and options are examined within the context of providing a high-integrity, low-leachability glass/ceramic, final waste form material. Thermal processing conditions required and capability of key systems components (equipment) to provide these material process conditions are considered. Information from closely related companion study reports on melter technology development needs assessment and INEL Iron-Enriched Basalt (IEB) research are considered. Five potentially practicable thermal process system design configuration concepts are defined and compared. A scenario for thermal processing of a mixed waste and soils stream with essentially no complex presorting and using a series process of incineration and high temperature melting is recommended. Recommendations for applied research and development necessary to further detail and demonstrate the final waste form, required thermal processes, and melter process equipment are provided.

Eddy, T.L.; Kong, P.C.; Raivo, B.D.; Anderson, G.L.

1992-02-01T23:59:59.000Z

194

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

SciTech Connect

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

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

1994-06-01T23:59:59.000Z

195

Sodium Bearing Waste Processing Alternatives Analysis  

SciTech Connect

A multidisciplinary team gathered to develop a BBWI recommendation to DOE-ID on the processing alternatives for the sodium bearing waste in the INTEC Tank Farm. Numerous alternatives were analyzed using a rigorous, systematic approach. The data gathered were evaluated through internal and external peer reviews for consistency and validity. Three alternatives were identified to be top performers: Risk-based Calcination, MACT to WIPP Calcination and Cesium Ion Exchange. A dual-path through early Conceptual design is recommended for MACT to WIPP Calcination and Cesium Ion Exchange since Risk-based Calcination does not require design. If calcination alternatives are not considered based on giving Type of Processing criteria significantly greater weight, the CsIX/TRUEX alternative follows CsIX in ranking. However, since CsIX/TRUEX shares common uncertainties with CsIX, reasonable backups, which follow in ranking, are the TRUEX and UNEX alternatives. Key uncertainties must be evaluated by the decision-makers to choose one final alternative. Those key uncertainties and a path forward for the technology roadmapping of these alternatives is provided.

Murphy, James Anthony; Palmer, Brent J; Perry, Keith Joseph

2003-12-01T23:59:59.000Z

196

Waste Processing and Recycling: Some Case Studies  

Science Conference Proceedings (OSTI)

Symposium, WASTE RECYCLING IN MINERAL AND METALLURGICAL ... Effect of Electricity Mix and Ore Grade on the Carbon Footprint of Chilean Cathodic ...

197

Stored program digital process controller  

DOE Patents (OSTI)

A digital process control function generator wherein a timing clock, in conjunction with programmable read only memories controls variables in a process with respect to time.

Stephenson, Dwight L. (Los Alamos, NM)

1977-01-04T23:59:59.000Z

198

Summary of national and international fuel cycle and radioactive waste management programs, 1984  

SciTech Connect

Worldwide activities related to nuclear fuel cycle and radioactive waste management programs are summarized. Several trends have developed in waste management strategy: All countries having to dispose of reprocessing wastes plan on conversion of the high-level waste (HLW) stream to a borosilicate glass and eventual emplacement of the glass logs, suitably packaged, in a deep geologic repository. Countries that must deal with plutonium-contaminated waste emphasize pluonium recovery, volume reduction and fixation in cement or bitumen in their treatment plans and expect to use deep geologic repositories for final disposal. Commercially available, classical engineering processing are being used worldwide to treat and immobilize low- and intermediate-level wastes (LLW, ILW); disposal to surface structures, shallow-land burial and deep-underground repositories, such as played-out mines, is being done widely with no obvious technical problems. Many countries have established extensive programs to prepare for construction and operation of geologic repositories. Geologic media being studied fall into three main classes: argillites (clay or shale); crystalline rock (granite, basalt, gneiss or gabbro); and evaporates (salt formations). Most nations plan to allow 30 years or longer between discharge of fuel from the reactor and emplacement of HLW or spent fuel is a repository to permit thermal and radioactive decay. Most repository designs are based on the mined-gallery concept, placing waste or spent fuel packages into shallow holes in the floor of the gallery. Many countries have established extensive and costly programs of site evaluation, repository development and safety assessment. Two other waste management problems are the subject of major R and D programs in several countries: stabilization of uranium mill tailing piles; and immobilization or disposal of contaminated nuclear facilities, namely reactors, fuel cycle plants and R and D laboratories.

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

1984-07-01T23:59:59.000Z

199

Optimal evaluation of infectious medical waste disposal companies using the fuzzy analytic hierarchy process  

SciTech Connect

Ever since Taiwan's National Health Insurance implemented the diagnosis-related groups payment system in January 2010, hospital income has declined. Therefore, to meet their medical waste disposal needs, hospitals seek suppliers that provide high-quality services at a low cost. The enactment of the Waste Disposal Act in 1974 had facilitated some improvement in the management of waste disposal. However, since the implementation of the National Health Insurance program, the amount of medical waste from disposable medical products has been increasing. Further, of all the hazardous waste types, the amount of infectious medical waste has increased at the fastest rate. This is because of the increase in the number of items considered as infectious waste by the Environmental Protection Administration. The present study used two important findings from previous studies to determine the critical evaluation criteria for selecting infectious medical waste disposal firms. It employed the fuzzy analytic hierarchy process to set the objective weights of the evaluation criteria and select the optimal infectious medical waste disposal firm through calculation and sorting. The aim was to propose a method of evaluation with which medical and health care institutions could objectively and systematically choose appropriate infectious medical waste disposal firms.

Ho, Chao Chung, E-mail: ho919@pchome.com.tw [Department of Industrial Management, National Taiwan University of Science and Technology, Taipei, Taiwan (China)

2011-07-15T23:59:59.000Z

200

Iraq liquid radioactive waste tanks maintenance and monitoring program plan.  

SciTech Connect

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

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

2011-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste processing program" 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

Process development for remote-handled mixed-waste treatment  

SciTech Connect

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

202

Waste Isolation Pilot Plant, National Transuranic Program Have Banner Year  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Plant, National Transuranic Program Have Plant, National Transuranic Program Have Banner Year in 2013 Waste Isolation Pilot Plant, National Transuranic Program Have Banner Year in 2013 December 24, 2013 - 12:00pm Addthis Since WIPP became operational in March 1999, it has surpassed receiving 11,000 shipments, which traveled over 14 million safe loaded miles over the nation’s highways through WIPP’s transportation program — equal to about 29 trips around the moon. WIPP has permanently disposed of more than 89,000 cubic meters of TRU waste — enough to fill more than 35 Olympic-size swimming pools. In 2013, WIPP is on course in support of the Los Alamos National Laboratory framework agreement with the State of New Mexico for complete removal of the above ground TRU waste stored at Area G by June 30, 2014. WIPP has cleaned 22 sites of legacy TRU waste.

203

Independent Oversight Review, Savannah River Site Salt Waste Processing  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Savannah River Site Salt Waste Savannah River Site Salt Waste Processing Facility - August 2013 Independent Oversight Review, Savannah River Site Salt Waste Processing Facility - August 2013 August 2013 Review of the Savannah River Site Salt Waste Processing Facility Safety Basis and Design Development. This report documents the results of an independent oversight review of the safety basis and design development for the Salt Waste Processing Facility (SWPF) at the U.S. Department of Energy (DOE) Savannah River Site. The review was performed February 12-14, 2013 by DOE's Office of Safety and Emergency Management Evaluations, which is within the DOE Office of Health, Safety and Security. The purpose of the review was to evaluate the safety basis, design, and the associated technical documents developed for

204

Independent Oversight Review, Savannah River Site Salt Waste Processing  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Savannah River Site Salt Waste Savannah River Site Salt Waste Processing Facility - August 2013 Independent Oversight Review, Savannah River Site Salt Waste Processing Facility - August 2013 August 2013 Review of the Savannah River Site Salt Waste Processing Facility Safety Basis and Design Development. This report documents the results of an independent oversight review of the safety basis and design development for the Salt Waste Processing Facility (SWPF) at the U.S. Department of Energy (DOE) Savannah River Site. The review was performed February 12-14, 2013 by DOE's Office of Safety and Emergency Management Evaluations, which is within the DOE Office of Health, Safety and Security. The purpose of the review was to evaluate the safety basis, design, and the associated technical documents developed for

205

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

206

Tank waste remediation system environmental program plan  

SciTech Connect

This Environmental Program Plan has been developed in support of the Integrated Environmental, Safety and Health Management System and consistent with the goals of DOE/RL-96-50, Hanford Strategic Plan (RL 1996a), and the specifications and guidance for ANSI/ISO 14001-1996, Environmental Management Systems Specification with guidance for use (ANSI/ISO 1996).

Borneman, L.E.

1998-01-09T23:59:59.000Z

207

Double Shell Tank (DST) Process Waste Sampling Subsystem Definition Report  

Science Conference Proceedings (OSTI)

This report defines the Double-Shell Tank (DST) Process Waste Sampling Subsystem (PWSS). This subsystem definition report fully describes and identifies the system boundaries of the PWSS. This definition provides a basis for developing functional, performance, and test requirements (i.e., subsystem specification), as necessary, for the PWSS. The resultant PWSS specification will include the sampling requirements to support the transfer of waste from the DSTs to the Privatization Contractor during Phase 1 of Waste Feed Delivery.

RASMUSSEN, J.H.

2000-04-25T23:59:59.000Z

208

Mixed and Low-Level Waste Treatment Facility project. Executive summary: Volume 1, Program summary information; Volume 2, Waste stream technical summary: Draft  

SciTech Connect

Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. The engineering studies, initiated in July 1991, identified 37 mixed waste streams, and 55 low-level waste streams. This report documents the waste stream information and potential treatment strategies, as well as the regulatory requirements for the Department of Energy-owned treatment facility option. The total report comprises three volumes and two appendices. This report consists of Volume 1, which explains the overall program mission, the guiding assumptions for the engineering studies, and summarizes the waste stream and regulatory information, and Volume 2, the Waste Stream Technical Summary which, encompasses the studies conducted to identify the INEL`s waste streams and their potential treatment strategies.

1992-04-01T23:59:59.000Z

209

RESULTS OF THE EXTRACTION-SCRUB-STRIP TESTING USING AN IMPROVED SOLVENT FORMULATION AND SALT WASTE PROCESSING FACILITY SIMULATED WASTE  

Science Conference Proceedings (OSTI)

The Office of Waste Processing, within the Office of Technology Innovation and Development, is funding the development of an enhanced solvent - also known as the next generation solvent (NGS) - for deployment at the Savannah River Site to remove cesium from High Level Waste. The technical effort is a collaborative effort between Oak Ridge National Laboratory (ORNL) and Savannah River National Laboratory (SRNL). As part of the program, the Savannah River National Laboratory (SRNL) has performed a number of Extraction-Scrub-Strip (ESS) tests. These batch contact tests serve as first indicators of the cesium mass transfer solvent performance with actual or simulated waste. The test detailed in this report used simulated Tank 49H material, with the addition of extra potassium. The potassium was added at 1677 mg/L, the maximum projected (i.e., a worst case feed scenario) value for the Salt Waste Processing Facility (SWPF). The results of the test gave favorable results given that the potassium concentration was elevated (1677 mg/L compared to the current 513 mg/L). The cesium distribution value, DCs, for extraction was 57.1. As a comparison, a typical D{sub Cs} in an ESS test, using the baseline solvent formulation and the typical waste feed, is {approx}15. The Modular Caustic Side Solvent Extraction Unit (MCU) uses the Caustic-Side Solvent Extraction (CSSX) process to remove cesium (Cs) from alkaline waste. This process involves the use of an organic extractant, BoBCalixC6, in an organic matrix to selectively remove cesium from the caustic waste. The organic solvent mixture flows counter-current to the caustic aqueous waste stream within centrifugal contactors. After extracting the cesium, the loaded solvent is stripped of cesium by contact with dilute nitric acid and the cesium concentrate is transferred to the Defense Waste Processing Facility (DWPF), while the organic solvent is cleaned and recycled for further use. The Salt Waste Processing Facility (SWPF), under construction, will use the same process chemistry. The Office of Waste Processing (EM-31) expressed an interest in investigating the further optimization of the organic solvent by replacing the BoBCalixC6 extractant with a more efficient extractant. This replacement should yield dividends in improving cesium removal from the caustic waste stream, and in the rate at which the caustic waste can be processed. To that end, EM-31 provided funding for both the Savannah River National Laboratory (SRNL) and the Oak Ridge National Laboratory (ORNL). SRNL wrote a Task Technical Quality and Assurance Plan for this work. As part of the envisioned testing regime, it was decided to perform an ESS test using a simulated waste that simulated a typical envisioned SWPF feed, but with added potassium to make the waste more challenging. Potassium interferes in the cesium removal, and its concentration is limited in the feed to <1950 mg/L. The feed to MCU has typically contained <500 mg/L of potassium.

Peters, T.; Washington, A.; Fink, S.

2012-01-09T23:59:59.000Z

210

UNITED STATES DEPARTMENT OF ENERGY WASTE PROCESSING ANNUAL TECHNOLOGY DEVELOPMENT REPORT 2007  

SciTech Connect

The Office of Environmental Management's (EM) Roadmap, U.S. Department of Energy--Office of Environmental Management Engineering & Technology Roadmap (Roadmap), defines the Department's intent to reduce the technical risk and uncertainty in its cleanup programs. The unique nature of many of the remaining facilities will require a strong and responsive engineering and technology program to improve worker and public safety, and reduce costs and environmental impacts while completing the cleanup program. The technical risks and uncertainties associated with cleanup program were identified through: (1) project risk assessments, (2) programmatic external technical reviews and technology readiness assessments, and (3) direct site input. In order to address these needs, the technical risks and uncertainties were compiled and divided into the program areas of: Waste Processing, Groundwater and Soil Remediation, and Deactivation and Decommissioning (D&D). Strategic initiatives were then developed within each program area to address the technical risks and uncertainties in that program area. These strategic initiatives were subsequently incorporated into the Roadmap, where they form the strategic framework of the EM Engineering & Technology Program. The EM-21 Multi-Year Program Plan (MYPP) supports the goals and objectives of the Roadmap by providing direction for technology enhancement, development, and demonstrations that will lead to a reduction of technical uncertainties in EM waste processing activities. The current MYPP summarizes the strategic initiatives and the scope of the activities within each initiative that are proposed for the next five years (FY2008-2012) to improve safety and reduce costs and environmental impacts associated with waste processing; authorized budget levels will impact how much of the scope of activities can be executed, on a year-to-year basis. As a result of the importance of reducing technical risk and uncertainty in the EM Waste Processing programs, EM-21 has focused considerable effort on identifying the key areas of risk in the Waste Processing programs. The resulting summary of technical risks and needs was captured in the Roadmap. The Roadmap identifies key Waste Processing initiative areas where technology development work should be focused. These areas are listed below, along with the Work Breakdown Structure (WBS) designation given to each initiative area. The WBS designations will be used throughout this document.

Bush, S

2008-08-12T23:59:59.000Z

211

Waste Heat Recovery from Industrial Process Heating Equipment -  

NLE Websites -- All DOE Office Websites (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

212

Polymer Solidification and Stabilization: Adaptable Processes for Atypical Wastes  

Science Conference Proceedings (OSTI)

Vinyl Ester Styrene (VES) and Advanced Polymer Solidification (APS{sup TM}) processes are used to solidify, stabilize, and immobilize radioactive, pyrophoric and hazardous wastes at US Department of Energy (DOE) and Department of Defense (DOD) sites, and commercial nuclear facilities. A wide range of projects have been accomplished, including in situ immobilization of ion exchange resin and carbon filter media in decommissioned submarines; underwater solidification of zirconium and hafnium machining swarf; solidification of uranium chips; impregnation of depth filters; immobilization of mercury, lead and other hazardous wastes (including paint chips and blasting media); and in situ solidification of submerged demineralizers. Discussion of the adaptability of the VES and APS{sup TM} processes is timely, given the decommissioning work at government sites, and efforts by commercial nuclear plants to reduce inventories of one-of-a-kind wastes. The VES and APS{sup TM} media and processes are highly adaptable to a wide range of waste forms, including liquids, slurries, bead and granular media; as well as metal fines, particles and larger pieces. With the ability to solidify/stabilize liquid wastes using high-speed mixing; wet sludges and solids by low-speed mixing; or bead and granular materials through in situ processing, these polymer will produce a stable, rock-hard product that has the ability to sequester many hazardous waste components and create Class B and C stabilized waste forms for disposal. Technical assessment and approval of these solidification processes and final waste forms have been greatly simplified by exhaustive waste form testing, as well as multiple NRC and CRCPD waste form approvals. (authors)

Jensen, C. [Diversified Technologies Services, Inc., Knoxville, TN (United States)

2007-07-01T23:59:59.000Z

213

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

SciTech Connect

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

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

1994-08-01T23:59:59.000Z

214

Waste heat driven absorption refrigeration process and system  

DOE Patents (OSTI)

Absorption cycle refrigeration processes and systems are provided which are driven by the sensible waste heat available from industrial processes and other sources. Systems are disclosed which provide a chilled water output which can be used for comfort conditioning or the like which utilize heat from sensible waste heat sources at temperatures of less than 170.degree. F. Countercurrent flow equipment is also provided to increase the efficiency of the systems and increase the utilization of available heat.

Wilkinson, William H. (Columbus, OH)

1982-01-01T23:59:59.000Z

215

Accelerator Production of Tritium project process waste assessment  

Science Conference Proceedings (OSTI)

DOE has made a commitment to compliance with all applicable environmental regulatory requirements. In this respect, it is important to consider and design all tritium supply alternatives so that they can comply with these requirements. The management of waste is an integral part of this activity and it is therefore necessary to estimate the quantities and specific wastes that will be generated by all tritium supply alternatives. A thorough assessment of waste streams includes waste characterization, quantification, and the identification of treatment and disposal options. The waste assessment for APT has been covered in two reports. The first report was a process waste assessment (PWA) that identified and quantified waste streams associated with both target designs and fulfilled the requirements of APT Work Breakdown Structure (WBS) Item 5.5.2.1. This second report is an expanded version of the first that includes all of the data of the first report, plus an assessment of treatment and disposal options for each waste stream identified in the initial report. The latter information was initially planned to be issued as a separate Waste Treatment and Disposal Options Assessment Report (WBS Item 5.5.2.2).

Carson, S.D.; Peterson, P.K.

1995-09-01T23:59:59.000Z

216

Tank waste remediation system nuclear criticality safety program management review  

SciTech Connect

This document provides the results of an internal management review of the Tank Waste Remediation System (TWRS) criticality safety program, performed in advance of the DOE/RL assessment for closure of the TWRS Nuclear Criticality Safety Issue, March 1994. Resolution of the safety issue was identified as Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-40-12, due September 1999.

BRADY RAAP, M.C.

1999-06-24T23:59:59.000Z

217

Recycling policy making of organic waste using analytical network process  

Science Conference Proceedings (OSTI)

The Analytic Hierarchy Process (AHP) has been used widely in multicriteria selection problems. However, AHP can deal with only a simple hierarchy of elements. On the other hand, the Analytical Network Process (ANP) can deal with more complex structures ... Keywords: analytical network process (ANP), group discussion, multicriteria selection, organic waste recycling policy making

Kazuei Ishii; Toru Furuichi

2008-11-01T23:59:59.000Z

218

Reliability analysis of common hazardous waste treatment processes  

Science Conference Proceedings (OSTI)

Five hazardous waste treatment processes are analyzed probabilistically using Monte Carlo simulation to elucidate the relationships between process safety factors and reliability levels. The treatment processes evaluated are packed tower aeration, reverse osmosis, activated sludge, upflow anaerobic sludge blanket, and activated carbon adsorption.

Waters, R.D. [Vanderbilt Univ., Nashville, TN (United States)

1993-05-01T23:59:59.000Z

219

The TEES process cleans waste and produces energy  

DOE Green Energy (OSTI)

A gasification system is under development that can be used with most types of wet organic wastes. The system operates at 350{degrees}C and 205 atm using a liquid water phase as the processing medium. Since a pressurized system is used, the wet waste can be fed as a solution or slurry to the reactor without drying. Through the development of catalysts, a useful processing system has been produced. The system has utility both for direct conversion of high-moisture biomass to fuel gas or as a wastewater cleanup system for wet organic wastes including unconverted biomass from bioconversion processes. By the use of this system >99% conversions of organic waste to medium-Btu fuel gas can be achieved.

Elliott, D.C.; Silva, L.J.

1995-02-01T23:59:59.000Z

220

Project Management Plan for the Idaho National Engineering Laboratory Waste Isolation Pilot Plant Experimental Test Program  

SciTech Connect

EG&G Idaho, Inc. and Argonne National Laboratory-West (ANL-W) are participating in the Idaho National Engineering Laboratory`s (INEL`s) Waste Isolation Pilot Plant (WIPP) Experimental Test Program (WETP). The purpose of the INEL WET is to provide chemical, physical, and radiochemical data on transuranic (TRU) waste to be stored at WIPP. The waste characterization data collected will be used to support the WIPP Performance Assessment (PA), development of the disposal No-Migration Variance Petition (NMVP), and to support the WIPP disposal decision. The PA is an analysis required by the Code of Federal Regulations (CFR), Title 40, Part 191 (40 CFR 191), which identifies the processes and events that may affect the disposal system (WIPP) and examines the effects of those processes and events on the performance of WIPP. A NMVP is required for the WIPP by 40 CFR 268 in order to dispose of land disposal restriction (LDR) mixed TRU waste in WIPP. It is anticipated that the detailed Resource Conservation and Recovery Act (RCRA) waste characterization data of all INEL retrievably-stored TRU waste to be stored in WIPP will be required for the NMVP. Waste characterization requirements for PA and RCRA may not necessarily be identical. Waste characterization requirements for the PA will be defined by Sandia National Laboratories. The requirements for RCRA are defined in 40 CFR 268, WIPP RCRA Part B Application Waste Analysis Plan (WAP), and WIPP Waste Characterization Program Plan (WWCP). This Project Management Plan (PMP) addresses only the characterization of the contact handled (CH) TRU waste at the INEL. This document will address all work in which EG&G Idaho is responsible concerning the INEL WETP. Even though EG&G Idaho has no responsibility for the work that ANL-W is performing, EG&G Idaho will keep a current status and provide a project coordination effort with ANL-W to ensure that the INEL, as a whole, is effectively and efficiently completing the requirements for WETP.

Connolly, M.J.; Sayer, D.L.

1993-11-01T23:59:59.000Z

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221

Enforcement Program and Process Guidance and Information | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Enforcement Program and Process Guidance and Information Enforcement Program and Process Guidance and Information The Safety and Security Enforcement Process Overview describes the...

222

IMPACT OF THE SMALL COLUMN ION EXCHANGE PROCESS ON THE DEFENSE WASTE PROCESSING FACILITY - 12112  

SciTech Connect

The Savannah River Site (SRS) is investigating the deployment of a parallel technology to the Salt Waste Processing Facility (SWPF, presently under construction) to accelerate high activity salt waste processing. The proposed technology combines large waste tank strikes of monosodium titanate (MST) to sorb strontium and actinides with two ion exchange columns packed with crystalline silicotitanate (CST) resin to sorb cesium. The new process was designated Small Column Ion Exchange (SCIX), since the ion exchange columns were sized to fit within a waste storage tank riser. Loaded resins are to be combined with high activity sludge waste and fed to the Defense Waste Processing Facility (DWPF) for incorporation into the current glass waste form. Decontaminated salt solution produced by SCIX will be fed to the SRS Saltstone Facility for on-site immobilization as a grout waste form. Determining the potential impact of SCIX resins on DWPF processing was the basis for this study. Accelerated salt waste treatment is projected to produce a significant savings in the overall life cycle cost of waste treatment at SRS.

Koopman, D.; Lambert, D.; Fox, K.; Stone, M.

2011-11-07T23:59:59.000Z

223

DOE Office of Waste Processing Technical Exchange - Agenda  

NLE Websites -- All DOE Office Websites (Extended Search)

June 1, 2009 June 1, 2009 Agenda Hotel Information Registration Presentation Guidelines Poster Guidelines Webcast Waiver Contacts Home Waste Processing Technical Exchange Agenda (Version 1.1) Pre-Registration: Monday, May 18, 5:00p - 7:00p Organizer/Session Chair: Blocker (early registration & speaker check-in) Day 1: Tuesday, May 19 Registration - 7:00a - 8:00a Session One - Opening Session Two - Waste Retrieval and Closure 1 Session Three - Waste Form Development Day 2: Wednesday, May 20 Session Four - Pretreatment 1 Session Five - Facility Readiness and Start-up Session Six - Pretreatment 2 Session Seven - Waste Retrieval and Closure 2 Session Eight - Poster Presentations Day 3: Thursday, May 21 Session Nine - Regulatory Activity and Performance Assessment Session Ten - Waste Storage and Tank Farm Operational Improvements

224

Hanford Small Scale Mixing Demonstration Program  

Hanford Small Scale Mixing Demonstration Program EM Waste Processing Technical Exchange November 17, 2010 Mike Thien

225

WASTE TREATMENT TECHNOLOGY PROCESS DEVELOPMENT PLAN FOR HANFORD WASTE TREATMENT PLANT LOW ACTIVITY WASTE RECYCLE  

SciTech Connect

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

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

2013-08-29T23:59:59.000Z

226

Process chemistry for the pretreatment of Hanford tank wastes  

SciTech Connect

Current guidelines for disposing radioactive wastes stored in underground tanks at the US Department of Energy`s Hanford Site call for the vitrification of high-level waste in borosilicate glass and disposal of the glass canisters in a deep geologic repository. Low-level waste is to be cast in grout and disposed of on site in shallow burial vaults. Because of the high cost of vitrification and geologic disposal, methods are currently being developed to minimize the volume of high-level waste requiring disposal. Two approaches are being considered for pretreating radioactive tank sludges: (1) leaching of selected components from the sludge and (2) acid dissolution of the sludge followed by separation of key radionuclides. The leaching approach offers the advantage of simplicity, but the acid dissolution/radionuclide extraction approach has the potential to produce the least number of glass canisters. Four critical components (Cr, P, S, and Al) were leached from an actual Hanford tank waste-Plutonium Finishing Plant sludge. The Al, P, and S were removed from the sludge by digestion of the sludge with 0.1 M NaOH at 100{degrees}C. The Cr was leached by treating the sludge with alkaline KMnO{sub 4} at 100{degrees}C. Removing these four components from the sludge will dramatically lower the number of glass canisters required to dispose of this waste. The transuranic extraction (TRUEX) solvent extraction process has been demonstrated at a bench scale using an actual Hanford tank waste. The process, which involves extraction of the transuranic elements with octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO), separated 99.9% of the transuranic elements from the bulk components of the waste. Several problems associated with the TRUEX processing of this waste have been addressed and solved.

Lumetta, G.J.; Swanson, J.L. [Pacific Northwest Lab., Richland, WA (United States); Barker, S.A. [Westinghouse Hanford Co., Richland, WA (United States)

1992-08-01T23:59:59.000Z

227

AISI waste oxide recycling program. Final technical report  

SciTech Connect

In March 1995 AISI completed a five-year, $60 million collaborative development program on Direct Steelmaking cost-shared by DOE under the Metals Initiative. This program defined an energy-efficient and environmentally-friendly technology to produce hot metal for steelmaking directly from coal and iron ore pellets without incurring the high capital costs and environmental problems associated with traditional coke oven and blast furnace technology. As it becomes necessary to replace present capacity, this new technology will be favored because of reduced capital costs, higher energy efficiency, and lower operating costs. In April 1994, having failed to move forward with a demonstration plant for direct ironmaking, despite substantial efforts by both Stelco and Geneva Steel, an alternative opportunity was sought to commercialize this new technology without waiting until existing ironmaking capacity needed to be replaced. Recycling and resource recovery of steel plant waste oxides was considered an attractive possibility. This led to approval of a ten-month, $8.3 million joint program with DOE on recycling steel plant waste oxides utilizing this new smelting technology. This highly successful trial program was completed in December 1994. The results of the pilot plant work and a feasibility study for a recycling demonstration plant are presented in this final technical report.

Aukrust, E.; Downing, K.B.; Sarma, B.

1995-08-01T23:59:59.000Z

228

Evaluation of a Mobile Hot Cell Technology for Processing Idaho National Laboratory Remote-Handled Wastes  

SciTech Connect

The Idaho National Laboratory (INL) currently does not have the necessary capabilities to process all remote-handled wastes resulting from the Laboratory’s nuclear-related missions. Over the years, various U.S. Department of Energy (DOE)-sponsored programs undertaken at the INL have produced radioactive wastes and other materials that are categorized as remote-handled (contact radiological dose rate > 200 mR/hr). These materials include Spent Nuclear Fuel (SNF), transuranic (TRU) waste, waste requiring geological disposal, low-level waste (LLW), mixed waste (both radioactive and hazardous per the Resource Conservation and Recovery Act [RCRA]), and activated and/or radioactively-contaminated reactor components. The waste consists primarily of uranium, plutonium, other TRU isotopes, and shorter-lived isotopes such as cesium and cobalt with radiological dose rates up to 20,000 R/hr. The hazardous constituents in the waste consist primarily of reactive metals (i.e., sodium and sodium-potassium alloy [NaK]), which are reactive and ignitable per RCRA, making the waste difficult to handle and treat. A smaller portion of the waste is contaminated with other hazardous components (i.e., RCRA toxicity characteristic metals). Several analyses of alternatives to provide the required remote-handling and treatment capability to manage INL’s remote-handled waste have been conducted over the years and have included various options ranging from modification of existing hot cells to construction of new hot cells. Previous analyses have identified a mobile processing unit as an alternative for providing the required remote-handled waste processing capability; however, it was summarily dismissed as being a potentially viable alternative based on limitations of a specific design considered. In 2008 INL solicited expressions of interest from Vendors who could provide existing, demonstrated technology that could be applied to the retrieval, sorting, treatment (as required), and repackaging of INL remote-handled wastes. Based on review of the responses and the potential viability of a mobile hot cell technology, INL subsequently conducted a technology evaluation, including proof-of-process validation, to assess the feasibility of utilizing such a technology for processing INL’s remote-handled wastes to meet established regulatory milestones. The technology evaluation focused on specific application of a mobile hot cell technology to the conditions to be encountered at the INL and addressed details of previous technology deployment, required modifications to accommodate INL’s remote-handled waste, ability to meet DOE safety requirements, requirements for fabrication/construction/decontamination and dismantling, and risks and uncertainties associated with application of the technology to INL’s remote-handled waste. The large capital costs associated with establishing a fixed asset to process INL’s remote-handled waste, the relatively small total volume of waste to be processed when compared to other waste streams through the complex, and competing mission-related needs has made it extremely difficult to secure the necessary support to advance the project. Because of this constraint, alternative contract structures were also explored as part of the technology evaluation wherein the impact of a large capital investment could be lessened.

B.J. Orchard; L.A. Harvego; R.P. Miklos; F. Yapuncich; L. Care

2009-03-01T23:59:59.000Z

229

Simulation of waste processing, transportation, and disposal operations  

E-Print Network (OSTI)

In response to the accelerated cleanup goals of the Department of Energy, Sandia National Laboratory (Sandia) has developed and utilized a number of simulation models to represent the processing, transportation, and disposal of radioactive waste. Sandia, in conjunction with Simulation Dynamics, has developed a Supply Chain model of the cradle to grave management of radioactive waste. Sandia has used this model to assist the Department of Energy in developing a cost effective, regulatory compliant and efficient approach to dispose of waste from 25 sites across the country over the next 35 years. 1

Janis Trone

2000-01-01T23:59:59.000Z

230

Simulation Of Waste Processing, Transportation, And Disposal Operations  

E-Print Network (OSTI)

In response to the accelerated cleanup goals of the Department of Energy, Sandia National Laboratory (Sandia) has developed and utilized a number of simulation models to represent the processing, transportation, and disposal of radioactive waste. Sandia, in conjunction with Simulation Dynamics, has developed a Supply Chain model of the cradle to grave management of radioactive waste. Sandia has used this model to assist the Department of Energy in developing a cost effective, regulatory compliant and efficient approach to dispose of waste from 25 sites across the country over the next 35 years.

J. A. Joines; R. R. Barton; K. Kang; P. A. Fishwick; Janis Trone; Angela Guerin

2000-01-01T23:59:59.000Z

231

Process to separate transuranic elements from nuclear waste  

DOE Patents (OSTI)

A process is described for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR). 2 figs.

Johnson, T.R.; Ackerman, J.P.; Tomczuk, Z.; Fischer, D.F.

1989-03-21T23:59:59.000Z

232

Process to separate transuranic elements from nuclear waste  

DOE Patents (OSTI)

A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR). 2 figs.

Johnson, T.R.; Ackerman, J.P.; Tomczuk, Z.; Fischer, D.F.

1988-07-12T23:59:59.000Z

233

Improved Process control of wood waste fired boilers  

DOE Green Energy (OSTI)

This project's principal aim was the conceptual and feasibility stage development of improved process control methods for wood-waste-fired water-tube boilers operating in industrial manufacturing applications (primarily pulp and paper). The specific objectives put forth in the original project proposal were as follows: (1) fully characterize the wood-waste boiler control inter-relationships and constraints through data collection and analysis; (2) design an improved control architecture; (3) develop and test an appropriate control and optimization algorithm; and (4) develop and test a procedure for reproducing the approach and deriving the benefits on similar pulp and paper wood-waste boilers. Detailed tasks were developed supporting these objectives.

Process Control Solutions, Inc.

2004-01-30T23:59:59.000Z

234

ALTERNATIVE THERMAL DESTRUCTION PROCESSES FOR HAZARDOUS WASTES  

E-Print Network (OSTI)

·Product Gas 400 2,000 11,300 Natural Gas 15,900 57,700 11,300 Most of these boilers are very small natural gas Distillate oil Natural gas Residual oil Distillate oil Natural gas Bituminous coal Bituminous coal Percent regulations. Candidate thermal processes include industrial processes such as boilers, process heaters, cement

Columbia University

235

TECHNOLOGY SUMMARY ADVANCING TANK WASTE RETREIVAL AND PROCESSING  

SciTech Connect

This technology overview provides a high-level summary of technologies being investigated and developed by Washington River Protection Solutions (WRPS) to advance Hanford Site tank waste retrieval and processing. Technology solutions are outlined, along with processes and priorities for selecting and developing them.

SAMS TL

2010-07-07T23:59:59.000Z

236

TECHNOLOGY SUMMARY ADVANCING TANK WASTE RETRIEVAL AND PROCESSING  

SciTech Connect

This technology overview provides a high-level summary of technologies being investigated and developed by Washington River Protection Solutions (WRPS) to advance Hanford Site tank waste retrieval and processing. Technology solutions are outlined, along with processes and priorities for selecting and developing them.

SAMS TL; MENDOZA RE

2010-08-11T23:59:59.000Z

237

Savannah River Site Salt Waste Processing Facility Technology Readiness Assessment Report  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Salt Waste Processing Facility Salt Waste Processing Facility Technology Readiness Assessment Report Kurt D. Gerdes Harry D. Harmon Herbert G. Sutter Major C. Thompson John R. Shultz Sahid C. Smith July 13, 2009 Prepared by the U.S. Department of Energy Washington, D.C. SRS Salt Waste Processing Facility Technology Readiness Assessment July 13, 2009 ii This page intentionally left blank SRS Salt Waste Processing Facility Technology Readiness Assessment July 13, 2009 iii SRS Salt Waste Processing Facility Technology Readiness Assessment July 13, 2009 iii Signatures SRS Salt Waste Processing Facility Technology Readiness Assessment July 13, 2009 iv This page intentionally left blank SRS Salt Waste Processing Facility

238

Savannah River Site - Salt Waste Processing Facility Independent Technical Review  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

SALT WASTE PROCESSING FACILITY SALT WASTE PROCESSING FACILITY INDEPENDENT TECHNICAL REVIEW November 22, 2006 Conducted by: Harry Harmon, Team Lead Civil/Structural Sub Team Facility Safety Sub Team Engineering Sub Team Peter Lowry, Lead James Langsted, Lead George Krauter, Lead Robert Kennedy Chuck Negin Art Etchells Les Youd Jerry Evatt Oliver Block Loring Wyllie Richard Stark Tim Adams Tom Anderson Todd LaPointe Stephen Gosselin Carl Costantino Norman Moreau Patrick Corcoran John Christian Ken Cooper Kari McDaniel _____________________________ Harry D. Harmon ITR Team Leader SPD-SWPF-217 SPD-SWPF-217: Salt Waste Processing Facility Independent Technical Review 11/22/2006 ACKNOWLEDGEMENT The ITR Team wishes to thank Shari Clifford of Pacific Northwest National Laboratory for

239

Microsoft PowerPoint - EM Waste 10-03 Processing Technical Exchange Antifoam 11-17-2010.ppt  

NLE Websites -- All DOE Office Websites (Extended Search)

664, Rev A 664, Rev A Improved Antifoam Agents for SRS Dan Lambert Fellow Engineer, SRNL Dr Darsh T. Wasan, Dr. Alex D. Nikolov, Illinois Institute of Technology EM Waste Processing Technical Exchange Session 10: Advanced Unit Operations and Scaling Print Close 2 SRNL-STI-2010-00698, Rev A Outline Needs/Benefits Background Scope Experimental/Method Results Future work Process Technology Programs Print Close 3 SRNL-STI-2010-00698, Rev A Needs/Benefits Needs: Increase waste processing (melter) throughput Benefits: Maximize Boilup Rate during waste processing at boiling, resulting in an increase in a reduction in overall processing time. Minimize carryover of insoluble solids, resulting in less facility downtime due to foamover into condensate. Process Technology Programs Print Close

240

Office of Civilian Radioactive Waste Management Transportation Program: Tribal Initiatives  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

COMMUNICATIONS BREAKOUT COMMUNICATIONS BREAKOUT SESSION Jay Jones Office of Civilian Radioactive Waste Management April 22, 2004 Albuquerque, New Mexico 2 Session Overview * Meeting objectives and expectations * Topic Group Background and History * Transportation information products - Information Product Survey results - Alliance for Transportation Research Institute Assessments * Discussion on future DOE communications * Information Display 3 Objectives and Expectations * OCRWM communications approach - Transportation Strategic Plan Collaborative effort with stakeholders Two-way interactions with program participants and public - provide information and receive feedback * Implement communications strategy - Identify stakeholders and issues - Engage nationally, regionally and with States - Participate through discussion and issue resolution

Note: This page contains sample records for the topic "waste processing program" 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

Demonstrating Reliable High Level Waste Slurry Sampling Techniques to Support Hanford Waste Processing - 14194  

SciTech Connect

The Hanford Tank Operations Contractor (TOC) and the Hanford Waste Treatment and Immobilization Plant (WTP) contractor are both engaged in demonstrating mixing, sampling, and transfer system capability using simulated Hanford High-Level Waste (HL W) formulations. This work represents one of the remaining technical issues with the high-level waste treatment mission at Hanford. The TOC must demonstrate the ability to adequately mix and sample high-level waste feed to meet the WTP Waste Acceptance Criteria and Data Quality Objectives. The sampling method employed must support both TOC and WTP requirements. To facilitate information transfer between the two facilities the mixing and sampling demonstrations are led by the One System Integrated Project Team. The One System team, Waste Feed Delivery Mixing and Sampling Program, has developed a full scale sampling loop to demonstrate sampler capability. This paper discusses the full scale sampling loops ability to meet precision and accuracy requirements, including lessons learned during testing. Results of the testing showed that the Isolok(R) sampler chosen for implementation provides precise, repeatable results. The Isolok(R) sampler accuracy as tested did not meet test success criteria. Review of test data and the test platform following testing by a sampling expert identified several issues regarding the sampler used to provide reference material used to judge the Isolok?'s accuracy. Recommendations were made to obtain new data to evaluate the sampler's accuracy utilizing a reference sampler that follows good sampling protocol.

Kelly, Steven E.

2013-11-11T23:59:59.000Z

242

SOLTECH 92 proceedings: Solar Process Heat Program  

SciTech Connect

This document is a limited Proceedings, documenting the presentations given at the symposia conducted by the US Department of Energy's (DOE) Solar Industrial Program and Solar Thermal Electrical Program at SOLTECH92. The SOLTECH92 national solar energy conference was held in Albuquerque, New Mexico during the period February 17--20, 1992. The National Renewable Energy Laboratory manages the Solar Industrial Program; Sandia National Laboratories (Albuquerque) manages the Solar Thermal Electric Program. The symposia sessions were as follows: (1) Solar Industrial Program and Solar Thermal Electric Program Overviews, (2) Solar Process Heat Applications, (3) Solar Decontamination of Water and Soil; (4) Solar Building Technologies, (5) Solar Thermal Electric Systems, (6) PV Applications and Technologies. For each presentation given in these symposia, these Proceedings provide a one- to two-page abstract and copies of the viewgraphs and/or 35mm slides utilized by the speaker. Some speakers provided additional materials in the interest of completeness. The materials presented in this document were not subjected to a peer review process.

1992-03-01T23:59:59.000Z

243

SOLTECH 92 proceedings: Solar Process Heat Program  

DOE Green Energy (OSTI)

This document is a limited Proceedings, documenting the presentations given at the symposia conducted by the US Department of Energy's (DOE) Solar Industrial Program and Solar Thermal Electrical Program at SOLTECH92. The SOLTECH92 national solar energy conference was held in Albuquerque, New Mexico during the period February 17--20, 1992. The National Renewable Energy Laboratory manages the Solar Industrial Program; Sandia National Laboratories (Albuquerque) manages the Solar Thermal Electric Program. The symposia sessions were as follows: (1) Solar Industrial Program and Solar Thermal Electric Program Overviews, (2) Solar Process Heat Applications, (3) Solar Decontamination of Water and Soil; (4) Solar Building Technologies, (5) Solar Thermal Electric Systems, (6) PV Applications and Technologies. For each presentation given in these symposia, these Proceedings provide a one- to two-page abstract and copies of the viewgraphs and/or 35mm slides utilized by the speaker. Some speakers provided additional materials in the interest of completeness. The materials presented in this document were not subjected to a peer review process.

Not Available

1992-03-01T23:59:59.000Z

244

Missouri Hazardous Waste Management Law (Missouri)  

Energy.gov (U.S. Department of Energy (DOE))

The Hazardous Waste Program, administered by the Hazardous Waste Management Commission in the Department of Natural Resources, regulates the processing, transportation, and disposal of hazardous...

245

Use of Chemical Pretreatment to Enhance Liquid Waste of Processing  

Science Conference Proceedings (OSTI)

This report details unique chemical pretreatment and processing techniques presently used by utilities in their nuclear plant liquid radwaste treatment programs. It presents specific utility experience from a number of plants employing these processing alternatives.

1999-04-23T23:59:59.000Z

246

Defense High-Level Waste Leaching Mechanisms Program. Final report  

SciTech Connect

The Defense High-Level Waste Leaching Mechanisms Program brought six major US laboratories together for three years of cooperative research. The participants reached a consensus that solubility of the leached glass species, particularly solubility in the altered surface layer, is the dominant factor controlling the leaching behavior of defense waste glass in a system in which the flow of leachant is constrained, as it will be in a deep geologic repository. Also, once the surface of waste glass is contacted by ground water, the kinetics of establishing solubility control are relatively rapid. The concentrations of leached species reach saturation, or steady-state concentrations, within a few months to a year at 70 to 90/sup 0/C. Thus, reaction kinetics, which were the main subject of earlier leaching mechanisms studies, are now shown to assume much less importance. The dominance of solubility means that the leach rate is, in fact, directly proportional to ground water flow rate. Doubling the flow rate doubles the effective leach rate. This relationship is expected to obtain in most, if not all, repository situations.

Mendel, J.E. (compiler)

1984-08-01T23:59:59.000Z

247

Waste Isolation Pilot Plant Groundwater Protection Management Program Plan  

SciTech Connect

U.S. Department of Energy (DOE) Order 5400.1, General Environmental Protection Program, requires each DOE site to prepare a Groundwater Protection Management Program Plan. This document fulfills the requirement for the Waste Isolation Pilot Plant (WIPP). This document was prepared by the Hydrology Section of the Westinghouse TRU Solutions LLC (WTS) Environmental Compliance Department, and it is the responsibility of this group to review the plan annually and update it every three years. This document is not, nor is it intended to be, an implementing document that sets forth specific details on carrying out field projects or operational policy. Rather, it is intended to give the reader insight to the groundwater protection philosophy at WIPP.

Washington TRU Solutions

2002-09-24T23:59:59.000Z

248

Sandia National Laboratories, California Waste Management Program annual report : February 2009.  

SciTech Connect

The annual program report provides detailed information about all aspects of the Sandia National Laboratories, California (SNL/CA) Waste Management Program. It functions as supporting documentation to the SNL/CA Environmental Management System rogram Manual. This annual program report describes the activities undertaken during the past year, and activities planned in future years to implement the Waste Management (WM) Program, one of six programs that supports environmental management at SNL/CA.

Brynildson, Mark E.

2009-02-01T23:59:59.000Z

249

Savannah River Site 2012 Outlook: Transuranic Waste Program Set to Safely  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Site 2012 Outlook: Transuranic Waste Program Set to Site 2012 Outlook: Transuranic Waste Program Set to Safely Reach Milestone Savannah River Site 2012 Outlook: Transuranic Waste Program Set to Safely Reach Milestone January 1, 2012 - 12:00pm Addthis By May, Savannah River Nuclear Solutions expects to be shipping transuranic waste to the Waste Isolation Pilot Plant almost continuously, using six TRUPACT-III shipping containers like the one shown here. By May, Savannah River Nuclear Solutions expects to be shipping transuranic waste to the Waste Isolation Pilot Plant almost continuously, using six TRUPACT-III shipping containers like the one shown here. Workers relocate a pipe overpack container used to transport small amounts of excess plutonium oxide destined for long-term storage at the Waste Isolation Pilot Plant in Carlsbad, New Mexico.

250

Waste Heat Management Options: Industrial Process Heating Systems  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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.

251

Savannah River Site - Salt Waste Processing Facility: Briefing on the Salt Waste Processing Facility Independent Technical Review  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Salt Waste Processing Facility Independent Technical Review Harry Harmon January 9, 2007 2 U.S. Department of Energy Outline * SWPF Process Overview * Major Risks * Approach for Conducting Review * Discussion of Findings * Conclusions 3 U.S. Department of Energy Salt Waste Processing Facility 4 U.S. Department of Energy SWPF Process Overview Alpha Finishing Process CSSX Alpha Strike Process MST/ Sludge Cs Strip Effluent DSS 5 U.S. Department of Energy BOTTOM LINE The SWPF Project is ready to move into final design. 6 U.S. Department of Energy Major Risks * Final geotechnical data potentially could result in redesign of the PC-3 CPA base mat and structure. * Cost and schedule impacts arising from the change from ISO-9001 to NQA-1 quality assurance requirements. * The "de-inventory, flush, and then hands-on

252

Foreign programs for the storage of spent nuclear power plant fuels, high-level waste canisters and transuranic wastes  

SciTech Connect

The various national programs for developing and applying technology for the interim storage of spent fuel, high-level radioactive waste, and TRU wastes are summarized. Primary emphasis of the report is on dry storage techniques for uranium dioxide fuels, but data are also provided concerning pool storage.

Harmon, K.M.; Johnson, A.B. Jr.

1984-04-01T23:59:59.000Z

253

Direction of CRT waste glass processing: Electronics recycling industry communication  

Science Conference Proceedings (OSTI)

Highlights: Black-Right-Pointing-Pointer Given a large flow rate of CRT glass {approx}10% of the panel glass stream will be leaded. Black-Right-Pointing-Pointer The supply of CRT waste glass exceeded demand in 2009. Black-Right-Pointing-Pointer Recyclers should use UV-light to detect lead oxide during the separation process. Black-Right-Pointing-Pointer Recycling market analysis techniques and results are given for CRT glass. Black-Right-Pointing-Pointer Academic initiatives and the necessary expansion of novel product markets are discussed. - Abstract: Cathode Ray Tube, CRT, waste glass recycling has plagued glass manufacturers, electronics recyclers and electronics waste policy makers for decades because the total supply of waste glass exceeds demand, and the formulations of CRT glass are ill suited for most reuse options. The solutions are to separate the undesirable components (e.g. lead oxide) in the waste and create demand for new products. Achieving this is no simple feat, however, as there are many obstacles: limited knowledge of waste glass composition; limited automation in the recycling process; transportation of recycled material; and a weak and underdeveloped market. Thus one of the main goals of this paper is to advise electronic glass recyclers on how to best manage a diverse supply of glass waste and successfully market to end users. Further, this paper offers future directions for academic and industry research. To develop the recommendations offered here, a combination of approaches were used: (1) a thorough study of historic trends in CRT glass chemistry; (2) bulk glass collection and analysis of cullet from a large-scale glass recycler; (3) conversations with industry members and a review of potential applications; and (4) evaluation of the economic viability of specific uses for recycled CRT glass. If academia and industry can solve these problems (for example by creating a database of composition organized by manufacturer and glass source) then the reuse of CRT glass can be increased.

Mueller, Julia R., E-mail: mueller.143@osu.edu [Ohio State University, William G. Lowrie Department of Chemical and Biomolecular Engineering, OH (United States) and University of Queensland, School of Chemical Engineering (Australia) and Ohio State University, Materials Science and Engineering, OH (United States); Boehm, Michael W. [University of Queensland, School of Chemical Engineering (Australia); Drummond, Charles [Ohio State University, Materials Science and Engineering, OH (United States)

2012-08-15T23:59:59.000Z

254

Technical Safety Requirements (TSR) for Waste Receiving & Processing (WRAP) facility  

SciTech Connect

These Technical Safety Requirements (TSRs) define the Administrative Controls required to ensure safe operation of the Waste Receiving and Processing Facility (WRAP). As will be shown in the report, Safety Limits, Limiting Control Settings, Limiting Conditions for Operation, and Surveillance Requirements are not required for safe operation of WRAP.

TOMASZEWSKI, T.A.

2001-07-10T23:59:59.000Z

255

Process for removal of sulfur oxides from waste gases  

Science Conference Proceedings (OSTI)

A process for removing sulfur oxides from waste gas is provided. The gas is contacted with a sorbent selected from sodium bicarbonate, trona and activated sodium carbonate and, utilizing an alkaline liquor containing borate ion so as to reduce flow rates and loss of alkalinity, the spent sorbent is regenerated with an alkaline earth metal oxide or hydroxide.

Lowell, P.S.; Phillips, J.L.

1983-05-24T23:59:59.000Z

256

ORNL long-range environmental and waste management plan: Program overview and summary  

SciTech Connect

The primary purpose of this report is to provide a thorough and systematic planning document to reflect the continuing process of site assessment, strategy development, and planning for the current and long-term control of environmental issues, waste management practices, and remedial action requirements. The docuemnt also provides an estimate of the resources required to implement the current plan. This document is not intended to be a budget document: it is, however, intended to provide guidance to both Martin Marietta Energy Systems, Inc., and the US Department of Energy (DOE) Management as to the near order of magnitude of the resources (primarily funding requirements) and the time frame required to execute the strategy in the present revision of the plan. The near-term (one to three years) part of the plan is a realistic assessment of the current program and ongoing capital projects and reflects the efforts preceived to be necessary to comply with all current state and federal regulations and DOE orders. It also should be in general agreement with current budget (funding) requests and obligations for these immediate years. Beyond the immediate time frame, the document reflects the strategy and the project and funding estimates as a snapshot at the time of publication. Annual revision will reflect the continuing evoltuion and development of environmental and waste management processes, characterizations, remedial actions, regulations, an strategies for the establishment and conduct of a comprehensive environmental and waste management program. 15 figs., 10 tabs.

Bates, L.D.; Berry, J.B.; Butterworth, G.E.; du Mont, S.P.; Easterday, C.A.; Geisler, A.H.; Hill, L.G.; Kendrick, C.M.; McNeese, L.E.; Myrick, T.E.; Pudelek, R.E.; Rohwer, P.S.; Scanlan, T.F.; Stratton, L.E.; Trabalka, J.R.; Youngblood, E.L.

1988-04-01T23:59:59.000Z

257

Vibratory Shear Enhanced Process Filtration for Processing Decommissioning Wastes at Rancho Seco  

Science Conference Proceedings (OSTI)

Many non-nuclear industries use a vibratory shear enhanced filtration process (VSEP) to separate solids in liquid streams. Unlike other methods, including the application of a precoat of filter media, the VSEP does not generate any secondary waste, making it seem ideally suited for nuclear power plant radwaste systems. This report presents the results of laboratory and pilot scale in-plant testing of VSEP's ability to successfully process radioactive decommissioning waste. Testing at Rancho Seco showed t...

2003-12-02T23:59:59.000Z

258

Electrochemical processing of nitrate waste solutions  

SciTech Connect

The second phase of research performed at The Electrosynthesis Co., Inc. has demonstrated the successful removal of nitrite and nitrate from a synthetic effluent stream via a direct electrochemical reduction at a cathode. It was shown that direct reduction occurs at good current efficiencies in 1,000 hour studies. The membrane separation process is not readily achievable for the removal of nitrites and nitrates due to poor current efficiencies and membrane stability problems. A direct reduction process was studied at various cathode materials in a flow cell using the complete synthetic mix. Lead was found to be the cathode material of choice, displaying good current efficiencies and stability in short and long term tests under conditions of high temperature and high current density. Several anode materials were studied in both undivided and divided cell configurations. A divided cell configuration was preferable because it would prevent re-oxidation of nitrite by the anode. The technical objective of eliminating electrode fouling and solids formation was achieved although anode materials which had demonstrated good stability in short term divided cell tests corroded in 1,000 hour experiments. The cause for corrosion is thought to be F[sup [minus

Genders, D.; Weinberg, N.; Hartsough, D. (Electrosynthesis Co., Inc., Cheektowaga, NY (United States))

1992-10-07T23:59:59.000Z

259

DOE site performance assessment activities. Radioactive Waste Technical Support Program  

Science Conference Proceedings (OSTI)

Information on performance assessment capabilities and activities was collected from eight DOE sites. All eight sites either currently dispose of low-level radioactive waste (LLW) or plan to dispose of LLW in the near future. A survey questionnaire was developed and sent to key individuals involved in DOE Order 5820.2A performance assessment activities at each site. The sites surveyed included: Hanford Site (Hanford), Idaho National Engineering Laboratory (INEL), Los Alamos National Laboratory (LANL), Nevada Test Site (NTS), Oak Ridge National Laboratory (ORNL), Paducah Gaseous Diffusion Plant (Paducah), Portsmouth Gaseous Diffusion Plant (Portsmouth), and Savannah River Site (SRS). The questionnaire addressed all aspects of the performance assessment process; from waste source term to dose conversion factors. This report presents the information developed from the site questionnaire and provides a comparison of site-specific performance assessment approaches, data needs, and ongoing and planned activities. All sites are engaged in completing the radioactive waste disposal facility performance assessment required by DOE Order 5820.2A. Each site has achieved various degrees of progress and have identified a set of critical needs. Within several areas, however, the sites identified common needs and questions.

Not Available

1990-07-01T23:59:59.000Z

260

Training Program EHS 604 ~ Hazardous Waste Generator Training  

NLE Websites -- All DOE Office Websites (Extended Search)

604 Hazardous Waste Generator Training Course Syllabus Subject Category: Waste Management Course Prerequisite: EHS0348 or equivalent Course Length: 45 minutes Medical Approval:...

Note: This page contains sample records for the topic "waste processing program" 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

Integrated process analysis of treatment systems for mixed low level waste  

SciTech Connect

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

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

1997-10-01T23:59:59.000Z

262

National low-level waste management program radionuclide report series, Volume 15: Uranium-238  

Science Conference Proceedings (OSTI)

This report, Volume 15 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of uranium-238 ({sup 238}U). The purpose of the National Low-Level Waste Management Program Radionuclide Report Series is to provide information to state representatives and developers of low-level radioactive waste disposal facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the waste disposal facility environment. This report also includes discussions about waste types and forms in which {sup 238}U can be found, and {sup 238}U behavior in the environment and in the human body.

Adams, J.P.

1995-09-01T23:59:59.000Z

263

Preliminary evaluation of alternative waste form solidification processes. Volume I. Identification of the processes.  

SciTech Connect

This document contains preconceptual design data on 11 processes for the solidification and isolation of nuclear high-level liquid wastes (HLLW). The processes are: in-can glass melting (ICGM) process, joule-heated glass melting (JHGM) process, glass-ceramic (GC) process, marbles-in-lead (MIL) matrix process, supercalcine pellets-in-metal (SCPIM) matrix process, pyrolytic-carbon coated pellets-in-metal (PCCPIM) matrix process, supercalcine hot-isostatic-pressing (SCHIP) process, SYNROC hot-isostatic-pressing (SYNROC HIP) process, titanate process, concrete process, and cermet process. For the purposes of this study, it was assumed that each of the solidification processes is capable of handling similar amounts of HLLW generated in a production-sized fuel reprocessing plant. It was also assumed that each of the processes would be enclosed in a shielded canyon or cells within a waste facility located at the fuel reprocessing plant. Finally, it was assumed that all of the processes would be subject to the same set of regulations, codes and standards. Each of the solidification processes converts waste into forms that may be acceptable for geological disposal. Each process begins with the receipt of HLLW from the fuel reprocessing plant. In this study, it was assumed that the original composition of the HLLW would be the same for each process. The process ends when the different waste forms are enclosed in canisters or containers that are acceptable for interim storage. Overviews of each of the 11 processes and the bases used for their identification are presented in the first part of this report. Each process, including its equipment and its requirements, is covered in more detail in Appendices A through K. Pertinent information on the current state of the art and the research and development required for the implementation of each process are also noted in the appendices.

Treat, R.L.; Nesbitt, J.F.; Blair, H.T.; Carter, J.G.; Gorton, P.S.; Partain, W.L.; Timmerman, C.L.

1980-04-01T23:59:59.000Z

264

Zero-Release Mixed Waste Process Facility Design and Testing  

SciTech Connect

A zero-release offgas cleaning system for mixed-waste thermal treatment processes has been evaluated through experimental scoping tests and process modeling. The principles can possibly be adapted to a fluidized-bed calcination or stream reforming process, a waste melter, a rotarykiln process, and possibly other waste treatment thermal processes. The basic concept of a zero-release offgas cleaning system is to recycle the bulk of the offgas stream to the thermal treatment process. A slip stream is taken off the offgas recycle to separate and purge benign constituents that may build up in the gas, such as water vapor, argon, nitrogen, and CO2. Contaminants are separated from the slip stream and returned to the thermal unit for eventual destruction or incorporation into the waste immobilization media. In the current study, a standard packed-bed scrubber, followed by gas separation membranes, is proposed for removal of contaminants from the offgas recycle slipstream. The scrub solution is continuously regenerated by cooling and precipitating sulfate, nitrate, and other salts that reach a solubility limit in the scrub solution. Mercury is also separated by the scrubber. A miscible chemical oxidizing agent was shown to effectively oxidize mercury and also NO, thus increasing their removal efficiency. The current study indicates that the proposed process is a viable option for reducing offgas emissions. Consideration of the proposed closed-system offgas cleaning loop is warranted when emissions limits are stringent, or when a reduction in the total gas emissions volume is desired. Although the current closed-loop appears to be technically feasible, economical considerations must be also be evaluated on a case-by-case basis.

Richard D. Boardman; John A. Deldebbio; Robert J. Kirkham; Martin K. Clemens; Robert Geosits; Ping Wan

2004-02-01T23:59:59.000Z

265

Waste Energy Analysis Recovery for a Typical Food Processing Plant  

E-Print Network (OSTI)

An energy analysis made for the Joan of Arc Food Processing Plant in St. Francisville, Louisiana indicated that a significant quantity of waste heat energy was being released to the atmosphere in the forms of low quality steam and hot flue gases. Additional analysis, measurements, and observations over a period of 12 months resulted in an evaluation of the losses as well as recommended methods for the effective recovery of the waste heat energy. The waste energy recovery results in significant savings in energy costs as well as a reduction in the consumption of scarce fuel. The research was supported by the Louisiana Department of Natural Resources, College of Engineering, Louisiana State University, and the Joan of Arc Company, St. Francisville, Louisiana.

Miller, P. H.; Mann, L., Jr.

1980-01-01T23:59:59.000Z

266

Suitability of Silica Gel to Process INEEL Sodium Bearing Waste - Letter Report  

SciTech Connect

The suitability of using the silica gel process for Idaho National Engineering and Environmental Laboratory (INEEL) sodium bearing waste was investigated during fiscal year 2000. The study was co-funded by the Tanks Focus Area as part of TTP No. ID-77WT-31 and the High Level Waste Program. The task also included the investigation of possible other absorbents. Scoping tests and examination of past work showed that the silica gel absorption/adsorption and drying method was the most promising; thus only silica gel was studied and not other absorbents. The documentation on the Russian silica gel process provided much of the needed information but did not provide some of the processing detail so these facts had to be inferred or gleaned from the literature.

Kirkham, Robert John; Herbst, Alan Keith

2000-09-01T23:59:59.000Z

267

Summary - SRS Salt Waste Processing Facility  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

SRS Co SRS Co DOE S Proces concen actinid in a se remov adjustm sorben sorben solutio passed separa stream extract sufficie separa (with S vitrifica (DWP Sr/acti federa assure and ha Critica The te (CTE) descrip Readin The Ele Site: S roject: S F Report Date: J ited States Why DOE omposite High Lev Savannah Rive ssing Facility (S ntrate targeted des) from High eries of unit ope ved by contactin ment) with a m nt in a batch m nt (containing S on by cross flow d to a solvent e ated to an aque m. The bulk so tion process, w ently low levels ated high activi Sr and actinide ation in the Def F). Provisions inides adsorpti al project direct e that the plann ave been matu al Decision-3 ap What th eam identified e of the SWPF w ption. All CTE ness Level of 6 To view the full T http://www.em.doe. objective of a Tech ements (CTEs), usin

268

Processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents (OSTI)

Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter.

Gotovchikov, Vitaly T. (Moscow, RU); Ivanov, Alexander V. (Moscow, RU); Filippov, Eugene A. (Moscow, RU)

1998-05-12T23:59:59.000Z

269

Processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents (OSTI)

Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter. 6 figs.

Gotovchikov, V.T.; Ivanov, A.V.; Filippov, E.A.

1998-05-12T23:59:59.000Z

270

Fractured rock modeling in the National Waste Terminal Storage Program: a review of requirements and status  

Science Conference Proceedings (OSTI)

Generalized computer codes capable of forming the basis for numerical models of fractured rock masses are being used within the NWTS program. Little additional development of these codes is considered justifiable, except in the area of representation of discrete fractures. On the other hand, model preparation requires definition of medium-specific constitutive descriptions and site characteristics and is therefore legitimately conducted by each of the media-oriented projects within the National Waste Terminal Storage program. However, it is essential that a uniform approach to the role of numerical modeling be adopted, including agreement upon the contribution of modeling to the design and licensing process and the need for, and means of, model qualification for particular purposes. This report discusses the role of numerical modeling, reviews the capabilities of several computer codes that are being used to support design or performance assessment, and proposes a framework for future numerical modeling activities within the NWTS program.

St. John, C.; Krug, A.; Key, S.; Monsees, J.

1983-05-01T23:59:59.000Z

271

Quality assurance program plan for low-level waste at the WSCF Laboratory  

Science Conference Proceedings (OSTI)

The purpose of this document is to provide guidance for the implementation of the Quality Assurance Program Plan (QAPP) for the management of low-level waste at the Waste Sampling and Characterization Facility (WSCF) Laboratory Complex as required by WHC-CM-4-2, Quality Assurance Manual, which is based on Quality Assurance Program Requirements for Nuclear Facilities, NQA-1 (ASME).

Morrison, J.A.

1994-11-01T23:59:59.000Z

272

Waste Isolation Pilot Plant Groundwater Protection Management Program Plan  

SciTech Connect

The DOE established the Groundwater Monitoring Program (GMP) (WP 02-1) to monitor groundwater resources at WIPP. In the past, the GMP was conducted to establish background data of existing conditions of groundwater quality and quantity in the WIPP vicinity, and to develop and maintain a water quality database as required by regulation. Today the GMP is conducted consistent with 204.1.500 NMAC (New MexicoAdministrative Code), "Adoption of 40 CFR [Code of Federal Regulations] Part 264,"specifically 40 CFR §264.90 through §264.101. These sections of 20.4.1 NMAC provide guidance for detection monitoring of groundwater that is, or could be, affected by waste management activities at WIPP. Detection monitoring at WIPP is designed to detect contaminants in the groundwater long before the general population is exposed. Early detection will allow cleanup efforts to be accomplished before any exposure to the general population can occur. Title 40 CFR Part 264, Subpart F, stipulates minimum requirements of Resource Conservation and Recovery Act of 1976 (42 United States Code [U.S.C.] §6901 et seq.) (RCRA) groundwater monitoring programs including the number and location of monitoring wells; sampling and reporting schedules; analytical methods and accuracy requirements; monitoring parameters; and statistical treatment of monitoring data. This document outlines how WIPP intends to protect and preserve groundwater within the WIPP Land Withdrawal Area (WLWA). Groundwater protection is just one aspect of the WIPP environmental protection effort. An overview of the entire environmental protection effort can be found in DOE/WIPP 99-2194, Waste Isolation Pilot Plant Environmental Monitoring Plan. The WIPP GMP is designed to statistically determine if any changes are occurring in groundwater characteristics within and surrounding the WIPP facility. If a change is noted, the cause will then be determined and the appropriate corrective action(s) initiated.

Washington Regulatory and Environmental Services

2005-07-01T23:59:59.000Z

273

Facility accident analysis for low-level waste management alternatives in the US Department of Energy Waste Management Program  

Science Conference Proceedings (OSTI)

The risk to human health of potential radiological releases resulting from facility accidents constitutes an important consideration in the US Department of Energy (DOE) waste management program. The DOE Office of Environmental Management (EM) is currently preparing a Programmatic Environmental Impact Statement (PEIS) that evaluates the risks associated with managing five types of radiological and chemical wastes in the DOE complex. Several alternatives for managing each of the five waste types are defined and compared in the EM PEIS. The alternatives cover a variety of options for storing, treating, and disposing of the wastes. Several treatment methods and operation locations are evaluated as part of the alternatives. The risk induced by potential facility accidents is evaluated for storage operations (current and projected waste storage and post-treatment storage) and for waste treatment facilities. For some of the five waste types considered, facility accidents cover both radiological and chemical releases. This paper summarizes the facility accident analysis that was performed for low-level (radioactive) waste (LLW). As defined in the EM PEIS, LLW includes all radioactive waste not classified as high-level, transuranic, or spent nuclear fuel. LLW that is also contaminated with chemically hazardous components is treated separately as low-level mixed waste (LLMW).

Roglans-Ribas, J.; Mueller, C.; Nabelssi, B.; Folga, S.; Tompkins, M.

1995-06-01T23:59:59.000Z

274

Process modeling of hydrogen production from municipal solid waste  

DOE Green Energy (OSTI)

The ASPEN PLUS commercial simulation software has been used to develop a process model for a conceptual process to convert municipal solid waste (MSW) to hydrogen. The process consists of hydrothermal treatment of the MSW in water to create a slurry suitable as feedstock for an oxygen blown Texaco gasifier. A method of reducing the complicated MSW feed material to a manageable set of components is outlined along with a framework for modeling the stoichiometric changes associated with the hydrothermal treatment process. Model results indicate that 0.672 kmol/s of hydrogen can be produced from the processing of 30 kg/s (2600 tonne/day) of raw MSW. A number of variations on the basic processing parameters are explored and indicate that there is a clear incentive to reduce the inert fraction in the processed slurry feed and that cofeeding a low value heavy oil may be economically attractive.

Thorsness, C.B.

1995-01-01T23:59:59.000Z

275

Idaho Site Taps Old World Process to Treat Nuclear Waste | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Idaho Site Taps Old World Process to Treat Nuclear Waste Idaho Site Taps Old World Process to Treat Nuclear Waste September 9, 2013 - 12:00pm Addthis The Idaho site's sodium...

276

SRNL PHASE 1 ASSESSMENT OF THE WAC/DQO AND UNIT OPERATIONS FOR THE WTP WASTE QUALIFICATION PROGRAM  

SciTech Connect

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is currently transitioning its emphasis from a design and construction phase toward start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements related to actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program to be implemented to support the WTP. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS), based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested the utilization of subject matter experts from SRNL to support a technology exchange to perform a review of the WTP waste qualification program, discuss the general qualification approach at SRS, and to identify critical lessons learned through the support of DWPF's sludge batch qualification efforts. As part of Phase 1, SRNL subject matter experts in critical technical and/or process areas reviewed specific WTP waste qualification information. The Phase 1 review was a collaborative, interactive, and iterative process between the two organizations. WTP provided specific analytical procedures, descriptions of equipment, and general documentation as baseline review material. SRNL subject matter experts reviewed the information and, as appropriate, requested follow-up information or clarification to specific areas of interest. This process resulted in multiple teleconferences with key technical contacts from both organizations resolving technical issues that lead to the results presented in this report. This report provides the results of SRNL's Phase 1 review of the WAC-DQO waste acceptance criteria and processability parameters, and the specific unit operations which are required to support WTP waste qualification efforts. The review resulted in SRNL providing concurrence, alternative methods, or gap identification for the proposed WTP analytical methods or approaches. For the unit operations, the SRNL subject matter experts reviewed WTP concepts compared to what is used at SRS and provided thoughts on the outlined tasks with respect to waste qualification. Also documented in this report are recommendations and an outline on what would be required for the next phase to further mature the WTP waste qualification program.

Peeler, D.; Adamson, D.; Bannochie, C.; Cozzi, A.; Eibling, R.; Hay, M.; Hansen, E.; Herman, D.; Martino, C.; Nash, C.; Pennebaker, F.; Poirier, M.; Reboul, S.; Stone, M.; Taylor-Pashow, K.; White, T.; Wilmarth, B.

2012-05-16T23:59:59.000Z

277

THE USE OF POLYMERS IN RADIOACTIVE WASTE PROCESSING SYSTEMS  

SciTech Connect

The Savannah River Site (SRS), one of the largest U.S. Department of Energy (DOE) sites, has operated since the early 1950s. The early mission of the site was to produce critical nuclear materials for national defense. Many facilities have been constructed at the SRS over the years to process, stabilize and/or store radioactive waste and related materials. The primary materials of construction used in such facilities are inorganic (metals, concrete), but polymeric materials are inevitably used in various applications. The effects of aging, radiation, chemicals, heat and other environmental variables must therefore be understood to maximize service life of polymeric components. In particular, the potential for dose rate effects and synergistic effects on polymeric materials in multivariable environments can complicate compatibility reviews and life predictions. The selection and performance of polymeric materials in radioactive waste processing systems at the SRS are discussed.

Skidmore, E.; Fondeur, F.

2013-04-15T23:59:59.000Z

278

Technical evaluation of the waste-to-oil process development facility at Albany, Oregon  

DOE Green Energy (OSTI)

The broad objective of ERDA's solar energy program at Albany, Oregon, is to develop biomass-to-synfuel technology in the Albany process development facility, which is now nearing completion. In the study reported here, the process development plant design was reevaluated, and a number of modifications and additions are recommended to facilitate and accelerate development of biomass conversion processes. Sketches of the recommended modifications and estimates of costs and installation time schedules have been provided. It has been found expedient to implement some of these modifications before construction is completed. Biomass-to-synfuel processes under development or under consideration elsewhere have been reviewed, and some have been identified that are appropriate for further development at Albany. Potential environmental impacts associated with the operation of the Albany, Oregon, facility were reviewed to identify the magnitude of the impacts and the effects of any resultant operational constraints. Two discrete environmental impact categories have been identified with respect to process development operation. These are (1) production, storage, and disposal of product oil and residual solid, liquid, and gaseous waste; and (2) disturbances to the local community. An assessment has been made of unit process waste discharges and mitigation procedures, environmental setting and community considerations, possible operational constraints, and monitoring programs.

Houle, E.H.; Ciriello, S.F.; Ergun, S.; Basuino, D.J.

1976-10-01T23:59:59.000Z

279

Program for certification of waste from contained firing facility: Establishment of waste as non-reactive and discussion of potential waste generation problems  

SciTech Connect

Debris from explosives testing in a shot tank that contains 4 weight percent or less of explosive is shown to be non-reactive under the specified testing protocol in the Code of Federal Regulations. This debris can then be regarded as a non-hazardous waste on the basis of reactivity, when collected and packaged in a specified manner. If it is contaminated with radioactive components (e.g. depleted uranium), it can therefore be disposed of as radioactive waste or mixed waste, as appropriate (note that debris may contain other materials that render it hazardous, such as beryllium). We also discuss potential waste generation issues in contained firing operations that are applicable to the planned new Contained Firing Facility (CFF). The goal of this program is to develop and document conditions under which shot debris from the planned Contained Firing Facility (CFF) can be handled, shipped, and accepted for waste disposal as non-reactive radioactive or mixed waste. This report fulfills the following requirements as established at the outset of the program: 1. Establish through testing the maximum level of explosive that can be in a waste and still have it certified as non-reactive. 2. Develop the procedure to confirm the acceptability of radioactive-contaminated debris as non-reactive waste at radioactive waste disposal sites. 3. Outline potential disposal protocols for different CFF scenarios (e.g. misfires with scattered explosive).

Green, L., Garza, R., Maienschein, J., Pruneda, C.

1997-09-30T23:59:59.000Z

280

Process Options Description for Vitrification Flowsheet Model of INEEL Sodium Bearing Waste  

SciTech Connect

The purpose of this document is to provide the technical information to Savannah River Site (SRS) personnel that is required for the development of a basic steady-state process simulation of the vitrification treatment train of sodium bearing waste (SBW) at Idaho National Engineering and nvironmental Laboratory (INEEL). INEEL considers simulation to have an important role in the integration/optimization of treatment process trains for the High Level Waste (HLW) Program. This project involves a joint Technical Task Plan (TTP ID77WT31, Subtask C) between SRS and INEEL. The work scope of simulation is different at the two sites. This document addresses only the treatment of SBW at INEEL. The simulation model(s) is to be built by SRS for INEEL in FY-2001.

Nichols, Todd Travis; Taylor, Dean Dalton; Lauerhass, Lance; Barnes, Charles Marshall

2001-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste processing program" 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

Waste and Water Top 2013 Accomplishments for Los Alamos EM Program |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Waste and Water Top 2013 Accomplishments for Los Alamos EM Program Waste and Water Top 2013 Accomplishments for Los Alamos EM Program Waste and Water Top 2013 Accomplishments for Los Alamos EM Program December 24, 2013 - 12:00pm Addthis Unusually heavy rain in early September caused flash flooding in canyons surrounding Los Alamos. Unusually heavy rain in early September caused flash flooding in canyons surrounding Los Alamos. LOS ALAMOS, N.M. - Los Alamos National Laboratory's biggest environmental cleanup accomplishments during 2013 centered around waste and water. The laboratory's 3706 TRU Waste Campaign, an accelerated shipping effort spurred by a massive wildfire in 2011, completed another record-breaking year in 2013, removing a cumulative 1,825 cubic meters of transuranic (TRU) waste and exceeding every previous shipping record.

282

Lessons learned in TRU waste process improvement at LANL  

SciTech Connect

Typical papers that discuss lessons learned or quality improvement focus on the challenge for a production facility reaching six sigma (3.4 Defects Per Million Opportunities) from five sigma. This paper discusses lessons learned when the Los Alamos National Laboratory's (LANL) transuranic (TRU) waste management project was challenged to establish a production system to meet the customer's expectations. The target for FY 2003 was set as two shipments of TRU waste per week leaving the site. The average for the four previous years (FY99-02) was about one shipment every two months. LANL recognized that, despite its success in 1999 as the first site to ship TRU waste to open the Waste Isolation Pilot Plant (WIPP), significant changes to the way business was being done were required to move to a production mode. Process improvements began in earnest in April 2002. This paper discusses several of the initiatives LANL took to achieve forty-five shipments in FY03. The paper is organized by topic into five major areas that LANL worked to get the job done.

Del Signore, J. C.; Huchton, J. (Judith); Martin, B. (Beverly); Lindahl, P. (Peter); Miller, S. (Scott); Hartwell, W. B. (Ware B.)

2004-01-01T23:59:59.000Z

283

Environmental Restoration Program waste minimization and pollution prevention self-assessment  

Science Conference Proceedings (OSTI)

The Environmental Restoration (ER) Program within Martin Marietta Energy Systems, Inc. is currently developing a more active waste minimization and pollution prevention program. To determine areas of programmatic improvements within the ER Waste Minimization and Pollution Prevention Awareness Program, the ER Program required an evaluation of the program across the Oak Ridge K-25 Site, the Oak Ridge National Laboratory, the Oak Ridge Y-12 Plant, the Paducah Environmental Restoration and Waste Minimization Site, and the Portsmouth Environmental Restoration and Waste Minimization Site. This document presents the status of the overall program as of fourth quarter FY 1994, presents pollution prevention cost avoidance data associated with FY 1994 activities, and identifies areas for improvement. Results of this assessment indicate that the ER Waste Minimization and Pollution Prevention Awareness Program is firmly established and is developing rapidly. Several procedural goals were met in FY 1994 and many of the sites implemented ER waste minimization options. Additional growth is needed, however, for the ER Waste Minimization and Pollution Prevention Awareness Program.

Not Available

1994-10-01T23:59:59.000Z

284

Performance Demonstration Program Plan for Nondestructive Assay for the TRU Waste Characterization Program. Revision 1  

Science Conference Proceedings (OSTI)

The Performance Demonstration Program (PDP) for Nondestructive Assay (NDA) consists of a series of tests conducted on a regular frequency to evaluate the capability for nondestructive assay of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed with TRU waste characterization systems. Measurement facility performance will be demonstrated by the successful analysis of blind audit samples according to the criteria set by this Program Plan. Intercomparison between measurement groups of the DOE complex will be achieved by comparing the results of measurements on similar or identical blind samples reported by the different measurement facilities. Blind audit samples (hereinafter referred to as PDP samples) will be used as an independent means to assess the performance of measurement groups regarding compliance with established Quality Assurance Objectives (QAOs). As defined for this program, a PDP sample consists of a 55-gallon matrix drum emplaced with radioactive standards and fabricated matrix inserts. These PDP sample components, once manufactured, will be secured and stored at each participating measurement facility designated and authorized by Carlsbad Area Office (CAO) under secure conditions to protect them from loss, tampering, or accidental damage.

None

1997-05-01T23:59:59.000Z

285

CRYSTALLINE CERAMIC WASTE FORMS: COMPARISON OF REFERENCE PROCESS FOR CERAMIC WASTE FORM FABRICATION  

SciTech Connect

The research conducted in this work package is aimed at taking advantage of the long term thermodynamic stability of crystalline ceramics to create more durable waste forms (as compared to high level waste glass) in order to reduce the reliance on engineered and natural barrier systems. Durable ceramic waste forms that incorporate a wide range of radionuclides have the potential to broaden the available disposal options and to lower the storage and disposal costs associated with advanced fuel cycles. Assemblages of several titanate phases have been successfully demonstrated to incorporate radioactive waste elements, and the multiphase nature of these materials allows them to accommodate variation in the waste composition. Recent work has shown that they can be produced from a melting and crystallization process. The objective of this report is to explore the phase formation and microstructural differences between lab scale melt processing in varying gas environments with alternative densification processes such as Hot Pressing (HP) and Spark Plasma Sintering (SPS). The waste stream used as the basis for the development and testing is a simulant derived from a combination of the projected Cs/Sr separated stream, the Trivalent Actinide - Lanthanide Separation by Phosphorous reagent Extraction from Aqueous Komplexes (TALSPEAK) waste stream consisting of lanthanide fission products, the transition metal fission product waste stream resulting from the transuranic extraction (TRUEX) process, and a high molybdenum concentration with relatively low noble metal concentrations. Melt processing as well as solid state sintering routes SPS and HP demonstrated the formation of the targeted phases; however differences in microstructure and elemental partitioning were observed. In SPS and HP samples, hollandite, pervoskite/pyrochlore, zirconolite, metallic alloy and TiO{sub 2} and Al{sub 2}O{sub 3} were observed distributed in a network of fine grains with small residual pores. The titanate phases that incorporate M{sup +3} rare earth elements were observed to be distinct phases (ex. Nd{sub 2}Ti{sub 2}O{sub 7}) with less degree of substitution as compared to the more homogeneous melt processed samples where a high degree of substitution and variation of composition within grains was observed. Liquid phase sintering was enhanced in reducing gas environments and resulted in large (10-200 microns) irregular shaped grains along with large voids associated with the melt process; SPS and HP samples exhibited finer grain size with smaller voids. Metallic alloys were observed in the bulk of the sample for SPS and HP samples, but were found at the bottom of the crucible in melt processed trials. These results indicate that for a first melter trial, the targeted phases can be formed in air by utilizing Ti/TiO{sub 2} additives which aid phase formation and improve the electrical conductivity. Ultimately, a melter run in reducing gas environments would be beneficial to study differences in phase formation and elemental partitioning.

Brinkman, K. S. [Savannah River National Laboratory; Marra, J. C. [Savannah River National Laboratory; Amoroso, J. [Savannah River National Laboratory; Tang, M. [Los Alamos National Laboratory

2013-08-22T23:59:59.000Z

286

Assessment of alternatives for management of ORNL retrievable transuranic waste. Nuclear Waste Program: transuranic waste (Activity No. AR 05 15 15 0; ONL-WT04)  

SciTech Connect

Since 1970, solid waste with TRU or U-233 contamination in excess of 10 ..mu..Ci per kilogram of waste has been stored in a retrievable fashion at ORNL, such as in ss drums, concrete casks, and ss-lined wells. This report describes the results of a study performed to identify and evaluate alternatives for management of this waste and of the additional waste projected to be stored through 1995. The study was limited to consideration of the following basic strategies: Strategy 1: Leave waste in place as is; Strategy 2: Improve waste confinement; and Strategy 3: Retrieve waste and process for shipment to a Federal repository. Seven alternatives were identified and evaluated, one each for Strategies 1 and 2 and five for Strategy 3. Each alternative was evaluated from the standpoint of technical feasibility, cost, radiological risk and impact, regulatory factors and nonradiological environmental impact.

Not Available

1980-10-01T23:59:59.000Z

287

New process effectively recovers oil from refinery waste streams  

Science Conference Proceedings (OSTI)

A new process uses chemically assisted, thermal flashing to break difficult emulsions and recover oil for reprocessing. The process is best suited for refinery waste management and slop oil systems, where it can process streams with high oil content to recover high-quality oil. Recent testing of a full-scale, commercial prototype unit on slop oil emulsions at a major Gulf Coast refinery resulted in: 97.9% recovery of oil with 99.3--99.6% purity; 99.5% recovery of water with 99+% purity; and a centrifuge cake containing 49-60% solids, 23--30 oil, and 17--22% water. The paper discusses background of the process, then gives a process description as well as results of field studies and cost.

Rhodes, A.

1994-08-15T23:59:59.000Z

288

Airborne Process Commercial Scale Demonstration Program  

NLE Websites -- All DOE Office Websites (Extended Search)

CCPI 2) CCPI 2) contacts Brad tomer Director Office of Major Demonstrations National Energy Technology Laboratory 3610 Collins Ferry Road P.O. Box 880 Morgantown, WV 26507-0880 304-285-4692 brad.tomer@netl.doe.gov PaRtIcIPant Mustang Clean Energy, LLC, a subsidiary of Peabody Energy St. Louis, MO. Airborne Process(tm) commerciAl scAle DemonstrAtion ProgrAm (withDrAwn Prior to AwArD) Project Description Mustang Clean Energy will design, construct, and operate a full scale sodium-based multi-pollutant scrubber in conjunction with a revenue-generating fertilizer by-product processing plant at Mustang Energy Company, LLC's Mustang Generating Station. Both Mustang Clean Energy and Mustang Energy Company are subsidiaries of Peabody Energy, the world's largest coal company. The 300 MW (net) station will

289

Review of Catalytic Hydrogen Generation in the Defense Waste Processing Facility (DWPF) Chemical Processing Cell  

DOE Green Energy (OSTI)

This report was prepared to fulfill the Phase I deliverable for HLW/DWPF/TTR-98-0018, Rev. 2, ''Hydrogen Generation in the DWPF Chemical Processing Cell'', 6/4/2001. The primary objective for the preliminary phase of the hydrogen generation study was to complete a review of past data on hydrogen generation and to prepare a summary of the findings. The understanding was that the focus should be on catalytic hydrogen generation, not on hydrogen generation by radiolysis. The secondary objective was to develop scope for follow-up experimental and analytical work. The majority of this report provides a summary of past hydrogen generation work with radioactive and simulated Savannah River Site (SRS) waste sludges. The report also includes some work done with Hanford waste sludges and simulants. The review extends to idealized systems containing no sludge, such as solutions of sodium formate and formic acid doped with a noble metal catalyst. This includes general information from the literature, as well as the focused study done by the University of Georgia for the SRS. The various studies had a number of points of universal agreement. For example, noble metals, such as Pd, Rh, and Ru, catalyze hydrogen generation from formic acid and formate ions, and more acid leads to more hydrogen generation. There were also some points of disagreement between different sources on a few topics such as the impact of mercury on the noble metal catalysts and the identity of the most active catalyst species. Finally, there were some issues of potential interest to SRS that apparently have not been systematically studied, e.g. the role of nitrite ion in catalyst activation and reactivity. The review includes studies covering the period from about 1924-2002, or from before the discovery of hydrogen generation during simulant sludge processing in 1988 through the Shielded Cells qualification testing for Sludge Batch 2. The review of prior studies is followed by a discussion of proposed experimental work, additional data analysis, and future modeling programs. These proposals have led to recent investigations into the mercury issue and the effect of co-precipitating noble metals which will be documented in two separate reports. SRS hydrogen generation work since 2002 will also be collected and summarized in a future report on the effect of noble metal-sludge matrix interactions on hydrogen generation. Other potential factors for experimental investigation include sludge composition variations related to both the washing process and to the insoluble species with particular attention given to the role of silver and to improving the understanding of the interaction of nitrite ion with the noble metals.

Koopman, D. C.

2004-12-31T23:59:59.000Z

290

GRR/Section 18-CO-b - Hazardous Waste Permit Process | Open Energy  

Open Energy Info (EERE)

GRR/Section 18-CO-b - Hazardous Waste Permit Process GRR/Section 18-CO-b - Hazardous Waste Permit Process < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-CO-b - Hazardous Waste Permit Process 18COBHazardousWastePermitProcess.pdf Click to View Fullscreen Contact Agencies Colorado Department of Public Health and Environment Regulations & Policies Colorado Hazardous Waste Regulations Part 260 Triggers None specified Click "Edit With Form" above to add content 18COBHazardousWastePermitProcess.pdf 18COBHazardousWastePermitProcess.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative Hazardous waste is a regulated substance and facilities that treat, store

291

GRR/Section 18-ID-b - Hazardous Waste Permit Process | Open Energy  

Open Energy Info (EERE)

GRR/Section 18-ID-b - Hazardous Waste Permit Process GRR/Section 18-ID-b - Hazardous Waste Permit Process < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-ID-b - Hazardous Waste Permit Process 18IDBHazardousWastePermitProcess.pdf Click to View Fullscreen Contact Agencies Idaho Department of Environmental Quality Regulations & Policies Idaho Hazardous Waste Management Act IDAPA 58.01.05 Rules and Standards for Hazardous Waste 40 CFR 124.31 Pre-application public meeting and notice 40 CRF 124.10 Public notice of permit actions and public comment period 40 CFR 124.12 Public hearings 40 CFR 270.13 Contents of Part A of the permit application Triggers None specified Click "Edit With Form" above to add content 18IDBHazardousWastePermitProcess.pdf 18IDBHazardousWastePermitProcess.pdf

292

Savannah River Site Waste Management Program Plan, FY 1993. Revision 1  

SciTech Connect

The primary purpose of the Waste Management Program Plan is to provide an annual report on facilities being used to manage wastes, forces acting to change current waste management (WM) systems, and how operations are conducted. This document also reports on plans for the coming fiscal year and projects activities for several years beyond the coming fiscal year to adequately plan for safe handling and disposal of radioactive wastes generated at the Savannah River Site (SRS) and for developing technology for improved management of wastes.

1993-06-01T23:59:59.000Z

293

Impact assessment of draft DOE Order 5820.2B. Radioactive Waste Technical Support Program  

SciTech Connect

The Department of Energy (DOE) has prepared a revision to DOE Order 5820.2A, entitled ``Radioactive Waste Management.`` DOE issued DOE Order 5820.2A in September 1988 and, as the title implies, it covered only radioactive waste forms. The proposed draft order, entitled ``Waste Management,`` addresses the management of both radioactive and nonradioactive waste forms. It also includes spent nuclear fuel, which DOE does not consider a waste. Waste forms covered include hazardous waste, high-level waste, transuranic (TRU) waste, low-level radioactive waste, uranium and thorium mill tailings, mixed waste, and sanitary waste. The Radioactive Waste Technical Support Program (TSP) of Leached Idaho Technologies Company (LITCO) is facilitating the revision of this order. The EM Regulatory Compliance Division (EM-331) has requested that TSP estimate the impacts and costs of compliance with the revised order. TSP requested Dames & Moore to aid in this assessment by comparing requirements in Draft Order 5820.2B to ones in DOE Order 5820.2A and other DOE orders and Federal regulations. The assessment started with a draft version of 5820.2B dated January 14, 1994. DOE has released three updated versions of the draft order since then (dated May 20, 1994; August 26, 1994; and January 23, 1995). Each time DOE revised the order, Dames and Moore updated the assessment work to reflect the text changes. This report reflects the January 23, 1995 version of the draft order.

NONE

1995-04-01T23:59:59.000Z

294

Defense Waste Processing Facility -- Radioactive operations -- Part 3 -- Remote operations  

SciTech Connect

The Savannah River Site`s Defense Waste Processing Facility (DWPF) near Aiken, South Carolina is the nation`s first and world`s largest vitrification facility. Following a ten year construction period and nearly three years of non-radioactive testing, the DWPF began radioactive operations in March 1996. Radioactive glass is poured from the joule heated melter into the stainless steel canisters. The canisters are then temporarily sealed, decontaminated, resistance welded for final closure, and transported to an interim storage facility. All of these operations are conducted remotely with equipment specially designed for these processes. This paper reviews canister processing during the first nine months of radioactive operations at DWPF. The fundamental design consideration for DWPF remote canister processing and handling equipment are discussed as well as interim canister storage.

Barnes, W.M.; Kerley, W.D.; Hughes, P.D.

1997-06-01T23:59:59.000Z

295

Evaluation program effectiveness of household hazardous waste collection: The Seattle-King County experience  

SciTech Connect

The Seattle-King County Hazardous Waste Management Plan provides the framework for an intensive effort to keep Household Hazardous and Small Quantity Generator (SQG) wastes from entering the normal'' municipal waste streams. The Plan sets ambitious goals for diverting thousands of tons of hazardous wastes from being thrown, poured or dumped in the municipal waste stream. During the first five years, over $30 millon will be spent for a variety of HHW and SQG programs. The Plan incorporates a wide range of elements, including education, collection, and compliance components. Many of the hazardous waste education and collection programs have been developed in response to the Plan, so their effectiveness is still undetermined. A key component of the Plan is program evaluation. This report provides descriptions of two evaluation methods used to establish baselines for assessing the effectiveness of the Hazardous Waste Management Plan's programs. Focusing on the Plan's household hazardous waste programs, the findings of the baseline evaluations are discussed and conclusions are made. A general population survey, conducted through telephone interviews, was designed to assess changes in knowledge, attitudes, and behaviors of area residents. Characterization of the solid waste stream was used to identify the hazardous constituents contributed to municipal solid waste by households. Monitoring changes in the amount of hazardous materials present in the waste stream was used to indicate whether or not Program strategies are influencing disposal behaviors. Comparing the data gathered by these two evaluation methods provided a unique opportunity to cross-check the findings and validate that change, if any, has occurred. From the comparisons, the report draws a number of conclusions.

1991-10-01T23:59:59.000Z

296

Tank 42 sludge-only process development for the Defense Waste Processing Facility (DWPF)  

SciTech Connect

Defense Waste Processing Facility (DWPF) requested the development of a sludge-only process for Tank 42 sludge since at the current processing rate, the Tank 51 sludge has been projected to be depleted as early as August 1998. Testing was completed using a non-radioactive Tank 42 sludge simulant. The testing was completed under a range of operating conditions, including worst case conditions, to develop the processing conditions for radioactive Tank 42 sludge. The existing Tank 51 sludge-only process is adequate with the exception that 10 percent additional acid is recommended during sludge receipt and adjustment tank (SRAT) processing to ensure adequate destruction of nitrite during the SRAT cycle.

Lambert, D.P.

2000-03-22T23:59:59.000Z

297

Conversion of historic waste treatment process for production of an LDR and WIPP/WAC compliant TRU wasteform  

SciTech Connect

In support of the historic weapons production mission at the, Rocky Flats Environmental Technology Site (RFETS), several liquid waste treatment processes were designed, built and operated for treatment of plutonium-contaminated aqueous waste. Most of these @ processes ultimately resulted in the production of a cemented wasteform. One of these treatment processes was the Miscellaneous Aqueous Waste Handling and Solidification Process, commonly referred to as the Bottlebox process. Due to a lack of processing demand, Bottlebox operations were curtailed in late 1989. Starting in 1992, a treatment capability for stabilization of miscellaneous, Resource Conservation and Recovery Act (RCRA) hazardous, plutonium-nitrate solutions was identified. This treatment was required to address potentially unsafe storage conditions for these liquids. The treatment would produce a TRU wasteform. It thus became necessary to restart the Bottlebox process, but under vastly different conditions and constraints than existed prior to its curtailment. This paper provides a description of the historical Bottlebox process and process controls; and then describes, in detail, all of the process and process control changes that were implemented to convert the treatment system such that a Waste Isolation Pilot Plant (WIPP) and a Land Disposal Requirements (LDR) compliant wasteform would be produced. The rationale for imposition of LDRs on a TRU wasteform is discussed. In addition, this paper discusses the program changes implemented to meet modem criticality safety, Conduct of Operations, and Department of Energy Nuclear Facility restart requirements.

Dunn, R.P.; Wagner, R.A.

1997-03-01T23:59:59.000Z

298

STATUS OF THE DEVELOPMENT OF IN-TANK/AT-TANK SEPARATIONS TECHNOLOGIES FOR FOR HIGH-LEVEL WASTE PROCESSING FOR THE U.S. DEPARTMENT OF ENERGY  

SciTech Connect

Within the U.S. Department of Energy's (DOE) Office of Technology Innovation and Development, the Office of Waste Processing manages a research and development program related to the treatment and disposition of radioactive waste. At the Savannah River (South Carolina) and Hanford (Washington) Sites, approximately 90 million gallons of waste are distributed among 226 storage tanks (grouped or collocated in 'tank farms'). This waste may be considered to contain mixed and stratified high activity and low activity constituent waste liquids, salts and sludges that are collectively managed as high level waste (HLW). A large majority of these wastes and associated facilities are unique to the DOE, meaning many of the programs to treat these materials are 'first-of-a-kind' and unprecedented in scope and complexity. As a result, the technologies required to disposition these wastes must be developed from basic principles, or require significant re-engineering to adapt to DOE's specific applications. Of particular interest recently, the development of In-tank or At-Tank separation processes have the potential to treat waste with high returns on financial investment. The primary objective associated with In-Tank or At-Tank separation processes is to accelerate waste processing. Insertion of the technologies will (1) maximize available tank space to efficiently support permanent waste disposition including vitrification; (2) treat problematic waste prior to transfer to the primary processing facilities at either site (i.e., Hanford's Waste Treatment and Immobilization Plant (WTP) or Savannah River's Salt Waste Processing Facility (SWPF)); and (3) create a parallel treatment process to shorten the overall treatment duration. This paper will review the status of several of the R&D projects being developed by the U.S. DOE including insertion of the ion exchange (IX) technologies, such as Small Column Ion Exchange (SCIX) at Savannah River. This has the potential to align the salt and sludge processing life cycle, thereby reducing the Defense Waste Processing Facility (DWPF) mission by 7 years. Additionally at the Hanford site, problematic waste streams, such as high boehmite and phosphate wastes, could be treated prior to receipt by WTP and thus dramatically improve the capacity of the facility to process HLW. Treatment of boehmite by continuous sludge leaching (CSL) before receipt by WTP will dramatically reduce the process cycle time for the WTP pretreatment facility, while treatment of phosphate will significantly reduce the number of HLW borosilicate glass canisters produced at the WTP. These and other promising technologies will be discussed.

Aaron, G.; Wilmarth, B.

2011-09-19T23:59:59.000Z

299

Process for Removing Radioactive Wastes from Liquid Streams  

SciTech Connect

The process is under development at Mound Laboratory to remove radioactive waste (principally plutonium-238) from process water prior to discharge of the water to the Miami river. The contaminated water, as normally received, is at a pH between 6 and 90. Under these conditions, plutonium in all its oxidation states is hydrolyzed; however, the level of the radioactive solids varies from about 50ppm down to about 50 ppb and the plutonium remains in a colloidal or subcolloidal condition. The permissible concentration for discharge to the river is about 50 parts per trillion. Pilot plant test show that 95-99% of the radioactive material is removed by adsorption on diatomaceous earth. The remainder is removed by passage through a bed of either dibasic or tribasic calcium phosphate. Ground phosphate rock is equally effective in removing the radioactive material if the flow rate is controlled to permit sufficient contact time. Parameters for optimizing the process are now under study. Future plans include application of the process to wastes from reactor fuels reprocessing.

Kirby, H. W.; Blane, D. E.; Smolin, R. I.

1972-10-01T23:59:59.000Z

300

GRR/Section 18-UT-b - Hazardous Waste Permit Process | Open Energy  

Open Energy Info (EERE)

UT-b - Hazardous Waste Permit Process UT-b - Hazardous Waste Permit Process < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-UT-b - Hazardous Waste Permit Process 18UTBHazardousWastePermitProcess (1).pdf Click to View Fullscreen Contact Agencies Utah Department of Environmental Quality Regulations & Policies Hazardous Waste Rules R315-1 et seq Triggers None specified Click "Edit With Form" above to add content 18UTBHazardousWastePermitProcess (1).pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative A hazardous waste is specifically listed by the Utah Solid and Hazardous Waste Rules or exhibits a characteristic such as ignitability, corrosivity,

Note: This page contains sample records for the topic "waste processing program" 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

Summary - Salt Waste Processing Facility Design at the Savannah River Site  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Salt Waste Processing Facility Salt Waste Processing Facility ETR Report Date: November 2006 ETR-4 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Salt Waste Processing Facility Design at the Savannah River Site (SRS) Why DOE-EM Did This Review The Salt Waste Processing Facility (SWPF) is intended to remove and concentrate the radioactive strontium (Sr), actinides, and cesium (Cs) from the bulk salt waste solutions in the SRS high-level waste tanks. The sludge and strip effluent from the SWPF that contain concentrated Sr, actinide, and Cs wastes will be sent to the SRS Defense Waste Processing Facility (DWPF), where they will be vitrified. The decontaminated salt solution (DSS) that is left after removal of the highly

302

Office of Enforcement -Enforcement Program and Process Guidance...  

NLE Websites -- All DOE Office Websites (Extended Search)

Program and Process Guidance and Information Office of Enforcement and Oversight The Safety and Security Enforcement Process Overview describes the Department of Energy's...

303

RCRA delisting of agent-decontaminated waste and remediation waste at Dugway Proving Ground: A program update  

Science Conference Proceedings (OSTI)

In July 1988, the state of Utah issued regulations that declared residues resulting from the demilitarization, treatment, and testing of military chemical agents to be hazardous wastes. These residues were designated as corrosive, reactive, toxic, and acute hazardous (Hazardous Waste No. F999). These residues are not listed by the U.S. Environmental Protection Agency (EPA) as hazardous waste under the Resource Conservation and Recovery Act (RCRA), which is the primary law governing management of hazardous waste in the United States. The RCRAI regulations (40 CFR 260-280), the Utah Administrative Code (R-315), and other state hazardous waste programs list specific wastes as hazardous but allow generators to petition the regulator to {open_quotes}delist{close_quotes} if it can be demonstrated that such wastes are not hazardous. In 1994, the U.S. Army Test and Evaluation Command FECOM initiated a project with the Argonne National Laboratory (Argonne) to demonstrate that certain categories of F999 residues are not hazardous waste and to achieve delisting. The initial focus is on delisting agent-decontaminated residues and soil with a history of contamination at the U.S. Army Dugway Proving Ground (DPG), Utah. An overview of the DPG delisting program was presented at the 1995 American Defense Preparedness Association Environmental Symposium. Since that time, much progress has been made. The purpose of this paper is to review the DPG delisting program and discuss overall progress. Emphasis is placed on progress with regard to analytical methods that will be used to demonstrate that the target residues do not contain hazardous amounts of chemical agent.

Kimmell, T.A.; Anderson, A.W.; O`Neill, H.J. [and others

1996-03-01T23:59:59.000Z

304

Solid Waste Processing Center Primary Opening Cells Systems, Equipment and Tools  

SciTech Connect

This document addresses the remote systems and design integration aspects of the development of the Solid Waste Processing Center (SWPC), a facility to remotely open, sort, size reduce, and repackage mixed low-level waste (MLLW) and transuranic (TRU)/TRU mixed waste that is either contact-handled (CH) waste in large containers or remote-handled (RH) waste in various-sized packages.

Bailey, Sharon A.; Baker, Carl P.; Mullen, O Dennis; Valdez, Patrick LJ

2006-04-17T23:59:59.000Z

305

Melt processing of radioactive waste: A technical overview  

Science Conference Proceedings (OSTI)

Nuclear operations have resulted in the accumulation of large quantities of contaminated metallic waste which are stored at various DOE, DOD, and commercial sites under the control of DOE and the Nuclear Regulatory Commission (NRC). This waste will accumulate at an increasing rate as commercial nuclear reactors built in the 1950s reach the end of their projected lives, as existing nuclear powered ships become obsolete or unneeded, and as various weapons plants and fuel processing facilities, such as the gaseous diffusion plants, are dismantled, repaired, or modernized. For example, recent estimates of available Radioactive Scrap Metal (RSM) in the DOE Nuclear Weapons Complex have suggested that as much as 700,000 tons of contaminated 304L stainless steel exist in the gaseous diffusion plants alone. Other high-value metals available in the DOE complex include copper, nickel, and zirconium. Melt processing for the decontamination of radioactive scrap metal has been the subject of much research. A major driving force for this research has been the possibility of reapplication of RSM, which is often very high-grade material containing large quantities of strategic elements. To date, several different single and multi-step melting processes have been proposed and evaluated for use as decontamination or recycling strategies. Each process offers a unique combination of strengths and weaknesses, and ultimately, no single melt processing scheme is optimum for all applications since processes must be evaluated based on the characteristics of the input feed stream and the desired output. This paper describes various melt decontamination processes and briefly reviews their application in developmental studies, full scale technical demonstrations, and industrial operations.

Schlienger, M.E.; Buckentin, J.M.; Damkroger, B.K.

1997-04-01T23:59:59.000Z

306

Mixed Waste Management Options: 1995 Update. National Low-Level Waste Management Program  

SciTech Connect

In the original mixed Waste Management Options (DOE/LLW-134) issued in December 1991, the question was posed, ``Can mixed waste be managed out of existence?`` That study found that most, but not all, of the Nation`s mixed waste can theoretically be managed out of existence. Four years later, the Nation is still faced with a lack of disposal options for commercially generated mixed waste. However, since publication of the original Mixed Waste Management Options report in 1991, limited disposal capacity and new technologies to treat mixed waste have become available. A more detailed estimate of the Nation`s mixed waste also became available when the US Environmental Protection Agency (EPA) and the US Nuclear Regulatory Commission (NRC) published their comprehensive assessment, titled National Profile on Commercially Generated Low-Level Radioactive Mixed Waste (National Profile). These advancements in our knowledge about mixed waste inventories and generation, coupled with greater treatment and disposal options, lead to a more applied question posed for this updated report: ``Which mixed waste has no treatment option?`` Beyond estimating the volume of mixed waste requiring jointly regulated disposal, this report also provides a general background on the Atomic Energy Act (AEA) and the Resource Conservation and Recovery Act (RCRA). It also presents a methodical approach for generators to use when deciding how to manage their mixed waste. The volume of mixed waste that may require land disposal in a jointly regulated facility each year was estimated through the application of this methodology.

Kirner, N.; Kelly, J.; Faison, G.; Johnson, D. [Foster Wheeler Environmental Corp. (United States)

1995-05-01T23:59:59.000Z

307

Order Module--self-study program: HAZARDOUS WASTE OPERATIONS AND EMERGENCY  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

self-study program: HAZARDOUS WASTE OPERATIONS AND self-study program: HAZARDOUS WASTE OPERATIONS AND EMERGENCY RESPONSE Order Module--self-study program: HAZARDOUS WASTE OPERATIONS AND EMERGENCY RESPONSE This module will discuss the objectives and requirements associated with this rule from the code of federal regulations. We have provided an example to help familiarize you with the material. The example will also help prepare you for the practice at the end of this module and for the criterion test. Before continuing, you should obtain a copy of the regulation at Hazardous waste operations and emergency response or through the course manager. You may need to refer to these documents to complete the example, practice, and criterion test. DOE Order Self Study Modules - 29 CFR 1910.120 Hazardous Waste Operations

308

Summary of non-US national and international radioactive waste management programs 1981  

SciTech Connect

Many nations and international agencies are working to develop improved technology and industrial capability for neuclear fuel cycle and waste management operations. The effort in some countries is limited to research in university laboratories on treating low-level waste from reactor plant operations. In other countries, national nuclear research institutes are engaged in major programs in all phases of the fuel cycle and waste management, and there is a national effort to commercialize fuel cycle operations. Since late 1976, staff members of Pacific Northwest Laboratory have been working under US Department of Energy sponsorship to assemble and consolidate openly available information on foreign and international nuclear waste management programs and technology. This report summarizes the information collected on the status of fuel cycle and waste management programs in selected countries making major efforts in these fields as of the end of May 1981.

Harmon, K.M.; Kelman, J.A.

1981-06-01T23:59:59.000Z

309

Summary of non-US national and international radioactive waste management programs 1980  

Science Conference Proceedings (OSTI)

Many nations and international agencies are working to develop improved technology and industrial capability for nuclear fuel cycle and waste management operations. The effort in some countries is limited to research in university laboratories on treating low-level waste from reactor plant operations. In other countries, national nuclear research institutes are engaged in major programs in all phases of the fuel cycle and waste management, and there is a national effort to commercialize fuel cycle operations. Since late 1976, staff members of Pacific Northwest Laboratory have been working under US Department of Energy sponsorship to assemble and consolidate openly available information on foreign and international nuclear waste management programs and technology. This report summarizes the information collected on the status of fuel cycle and waste management programs in selected countries making major efforts in these fields as of the end of January 1980.

Harmon, K.M.; Kelman, J.A.; Stout, L.A.; Hsieh, K.A.

1980-03-01T23:59:59.000Z

310

Modelling of environmental impacts of solid waste landfilling within the life-cycle analysis program EASEWASTE  

Science Conference Proceedings (OSTI)

A new computer-based life-cycle assessment model (EASEWASTE) has been developed to evaluate resource and environmental consequences of solid waste management systems. This paper describes the landfilling sub-model used in the life-cycle assessment program EASEWASTE, and examines some of the implications of this sub-model. All quantities and concentrations of leachate and landfill gas can be modified by the user in order to bring them in agreement with the actual landfill that is assessed by the model. All emissions, except the generation of landfill gas, are process specific. The landfill gas generation is calculated on the basis of organic matter in the landfilled waste. A landfill assessment example is provided. For this example, the normalised environmental effects of landfill gas on global warming and photochemical smog are much greater than the environmental effects for landfill leachate or for landfill construction. A sensitivity analysis for this example indicates that the overall environmental impact is sensitive to the gas collection efficiency and the use of the gas, but not to the amount of leachate generated, or the amount of soil or liner material used in construction. The landfill model can be used for evaluating different technologies with different liners, gas and leachate collection efficiencies, and to compare the environmental consequences of landfilling with alternative waste treatment options such as incineration or anaerobic digestion.

Kirkeby, Janus T.; Birgisdottir, Harpa [Environment and Resources, Technical University of Denmark, DTU, Building 113, DK-2800 Kgs. Lyngby (Denmark); Bhander, Gurbakash Singh; Hauschild, Michael [Department of Manufacturing Engineering and Management, Technical University of Denmark, Building 424, DK-2800 Lyngby (Denmark); Christensen, Thomas H. [Environment and Resources, Technical University of Denmark, DTU, Building 113, DK-2800 Kgs. Lyngby (Denmark)], E-mail: thc@er.dtu.dk

2007-07-01T23:59:59.000Z

311

RPP-PLAN-47325 Revision 0 Radioactive Waste Determination Process Plan for Waste Management Area C Tank  

E-Print Network (OSTI)

This plan describes the radioactive waste determination process that the U.S. Department of Energy (DOE) will use for Hanford Site Waste Management Area C (WMA C) tank waste residuals subject to DOE authority under DOE Order 435.1, Radioactive Waste Management. Preparation of this plan is a required component of actions the DOE-Office of River Protection (ORP) must take to fulfill proposed Hanford Federal Facility Agreement and Consent Order Milestone M-045-80. Waste Management Area C is comprised of various single-shell tanks, encased and direct-buried pipes, diversion boxes, pump pits, and unplanned release sites (sites contaminated as a result of spills of tank waste to the environment). Since operations began in the late 1940s, the tanks in WMA C have continuously stored waste managed as high-level waste (HLW) that was derived from defense-related nuclear research, development, and weapons production activities. Planning for the final closure of WMA C is underway. This radioactive waste determination process plan assumes that tank closure will follow retrieval of as much tank waste as technically and economically practical. It is also assumed for the purposes of this plan that after completion

Waste Residuals; J. R. Robertson

2010-01-01T23:59:59.000Z

312

Pyrochemical treatment of Idaho Chemical Processing Plant high-level waste calcine  

SciTech Connect

The Idaho Chemical Processing Plant (ICPP), located at the Idaho National Engineering Laboratory (INEL), has reprocessed irradiated nuclear fuels for the US Department of Energy (DOE) since 1951 to recover uranium, krypton-85, and isolated fission products for interim treatment and immobilization. The acidic radioactive high-level liquid waste (HLLW) is routinely stored in stainless steel tanks and then, since 1963, calcined to form a dry granular solid. The resulting high-level waste (HLW) calcine is stored in seismically hardened stainless steel bins that are housed in underground concrete vaults. A research and development program has been established to determine the feasibility of treating ICPP HLW calcine using pyrochemical technology.This technology is described.

Todd, T.A.; DelDebbio, J.A.; Nelson, L.O.; Sharpsten, M.R.

1993-06-01T23:59:59.000Z

313

Method for co-processing waste rubber and carbonaceous material  

DOE Green Energy (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

314

Method for co-processing waste rubber and carbonaceous material  

DOE Green Energy (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 depolymerized rubber acts as a liquefying solvent for the carbonaceous material while a beneficial catalytic effect is obtained from the carbon black released on depolymerization the reinforced rubber. The reaction is carried out at liquefaction conditions of 380.degree.-600.degree. 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, Malvina (Pittsburgh, PA); Smith, Charlene M. (Pittsburgh, PA)

1991-01-01T23:59:59.000Z

315

Feed Composition for Sodium-Bearing Waste Treatment Process  

SciTech Connect

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

Barnes, C.M.

2000-10-30T23:59:59.000Z

316

The Coal-Waste Artificial Reef Program (C-WARP): A New Resource  

E-Print Network (OSTI)

The Coal-Waste Artificial Reef Program (C-WARP): A New Resource Potential for Fishing Reef ABSTRACT-Thefeasibility ofusing solid blocks of waste materialfrom coal:firedpower plantslor underwater (scrubber) sludge from coal-burning power stations. was constructed in the Atlantic Ocean offLong Island. N

317

Chemical Disposal The Office of Environmental Health & Safety operates a Chemical Waste Disposal Program  

E-Print Network (OSTI)

Chemical Disposal Dec, 2011 Chemicals: The Office of Environmental Health & Safety operates a Chemical Waste Disposal Program where all University chemical waste is picked up and sent out for proper disposal. (There are some chemicals that they will not take because of their extreme hazards

Machel, Hans

318

National low-level waste management program radionuclide report series, Volume 14: Americium-241  

Science Conference Proceedings (OSTI)

This report, Volume 14 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of americium-241 ({sup 241}Am). This report also includes discussions about waste types and forms in which {sup 241}Am can be found and {sup 241}Am behavior in the environment and in the human body.

Winberg, M.R.; Garcia, R.S.

1995-09-01T23:59:59.000Z

319

Federal Energy Management Program: Municipal Solid Waste Resources...  

NLE Websites -- All DOE Office Websites (Extended Search)

The National Renewable Energy Laboratory's high-solids digester converts wastes to biogas and compost for energy production. This page provides a brief overview of municipal...

320

Federal Energy Management Program: ESPC ENABLE Procurement Process  

NLE Websites -- All DOE Office Websites (Extended Search)

Procurement Process to someone by E-mail Procurement Process to someone by E-mail Share Federal Energy Management Program: ESPC ENABLE Procurement Process on Facebook Tweet about Federal Energy Management Program: ESPC ENABLE Procurement Process on Twitter Bookmark Federal Energy Management Program: ESPC ENABLE Procurement Process on Google Bookmark Federal Energy Management Program: ESPC ENABLE Procurement Process on Delicious Rank Federal Energy Management Program: ESPC ENABLE Procurement Process on Digg Find More places to share Federal Energy Management Program: ESPC ENABLE Procurement Process on AddThis.com... Energy Savings Performance Contracts ENABLE Procurement Process Energy Service Company Options Project Assistance & Training Utility Energy Service Contracts On-Site Renewable Power Purchase Agreements

Note: This page contains sample records for the topic "waste processing program" 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

Tank Waste Remediation System tank waste pretreatment and vitrification process development testing requirements assessment  

Science Conference Proceedings (OSTI)

A multi-faceted study was initiated in November 1993 to provide assurance that needed testing capabilities, facilities, and support infrastructure (sampling systems, casks, transportation systems, permits, etc.) would be available when needed for process and equipment development to support pretreatment and vitrification facility design and construction schedules. This first major report provides a snapshot of the known testing needs for pretreatment, low-level waste (LLW) and high-level waste (HLW) vitrification, and documents the results of a series of preliminary studies and workshops to define the issues needing resolution by cold or hot testing. Identified in this report are more than 140 Hanford Site tank waste pretreatment and LLW/HLW vitrification technology issues that can only be resolved by testing. The report also broadly characterizes the level of testing needed to resolve each issue. A second report will provide a strategy(ies) for ensuring timely test capability. Later reports will assess the capabilities of existing facilities to support needed testing and will recommend siting of the tests together with needed facility and infrastructure upgrades or additions.

Howden, G.F.

1994-10-24T23:59:59.000Z

322

Tank waste remediation system process engineering instruction manual  

SciTech Connect

The purpose of the Tank Waste Remediation System (TWRS) Process Engineering Instruction Manual is to provide guidance and direction to TWRS Process Engineering staff regarding conduct of business. The objective is to establish a disciplined and consistent approach to business such that the work processes within TWRS Process Engineering are safe, high quality, disciplined, efficient, and consistent with Lockheed Martin Hanford Corporation Policies and Procedures. The sections within this manual are of two types: for compliance and for guidance. For compliance sections are intended to be followed per-the-letter until such time as they are formally changed per Section 2.0 of this manual. For guidance sections are intended to be used by the staff for guidance in the conduct of work where technical judgment and discernment are required. The guidance sections shall also be changed per Section 2.0 of this manual. The required header for each manual section is illustrated in Section 2.0, Manual Change Control procedure. It is intended that this manual be used as a training and indoctrination resource for employees of the TWRS Process Engineering organization. The manual shall be required reading for all TWRS Process Engineering staff, matrixed, and subcontracted employees.

ADAMS, M.R.

1998-11-04T23:59:59.000Z

323

Organic tanks safety program FY95 waste aging studies  

SciTech Connect

This report gives the second year`s findings of a study of how thermal and radiological processes may change the composition of organic compounds in the underground tanks at Hanford. Efforts were focused on the global reaction kinetics in a simulated waste exposed to {gamma} rays and the reactions of organic radicals with nitrite ion. The gas production is predominantly radiolytic. Decarboxylation of carboxylates is probably an aging pathway. TBP was totaly consumed in almost every run. Radiation clearly accelerated consumption of the other compounds. EDTA is more reactive than citrate. Oximes and possibly organic nitro compounds are key intermediates in the radiolytic redox reactions of organic compounds with nitrate/nitrite. Observations are consistent with organic compounds being progressively degraded to compounds with greater numbers of C-O bonds and fewer C-H and C-C bonds, resulting in an overall lower energy content. If the radwaste tanks are adequately ventilated and continually dosed by radioactivity, their total energy content should have declined. Level of risk depends on how rapidly carboxylate salts of moderate energy content (including EDTA fragments) degrade to low energy oxalate and formate.

Camaioni, D.M.; Samuels, W.D.; Clauss, S.A.; Lenihan, B.D.; Wahl, K.L.; Campbell, J.A.; Shaw, W.J.

1995-09-01T23:59:59.000Z

324

Process Knowledge Summary Report for Materials and Fuels Complex Contact-Handled Transuranic Debris Waste  

SciTech Connect

This Process Knowledge Summary Report summarizes the information collected to satisfy the transportation and waste acceptance requirements for the transfer of transuranic (TRU) waste between the Materials and Fuels Complex (MFC) and the Advanced Mixed Waste Treatment Project (AMWTP). The information collected includes documentation that addresses the requirements for AMWTP and the applicable portion of their Resource Conservation and Recovery Act permits for receipt and treatment of TRU debris waste in AMWTP. This report has been prepared for contact-handled TRU debris waste generated by the Idaho National Laboratory at MFC. The TRU debris waste will be shipped to AMWTP for purposes of supercompaction. This Process Knowledge Summary Report includes information regarding, but not limited to, the generation process, the physical form, radiological characteristics, and chemical contaminants of the TRU debris waste, prohibited items, and packaging configuration. This report, along with the referenced supporting documents, will create a defensible and auditable record for waste originating from MFC.

R. P. Grant; P. J. Crane; S. Butler; M. A. Henry

2010-02-01T23:59:59.000Z

325

Modeling Coupled Processes in Clay Formations for Radioactive Waste Disposal  

Science Conference Proceedings (OSTI)

As a result of the termination of the Yucca Mountain Project, the United States Department of Energy (DOE) has started to explore various alternative avenues for the disposition of used nuclear fuel and nuclear waste. The overall scope of the investigation includes temporary storage, transportation issues, permanent disposal, various nuclear fuel types, processing alternatives, and resulting waste streams. Although geologic disposal is not the only alternative, it is still the leading candidate for permanent disposal. The realm of geologic disposal also offers a range of geologic environments that may be considered, among those clay shale formations. Figure 1-1 presents the distribution of clay/shale formations within the USA. Clay rock/shale has been considered as potential host rock for geological disposal of high-level nuclear waste throughout the world, because of its low permeability, low diffusion coefficient, high retention capacity for radionuclides, and capability to self-seal fractures induced by tunnel excavation. For example, Callovo-Oxfordian argillites at the Bure site, France (Fouche et al., 2004), Toarcian argillites at the Tournemire site, France (Patriarche et al., 2004), Opalinus clay at the Mont Terri site, Switzerland (Meier et al., 2000), and Boom clay at Mol site, Belgium (Barnichon et al., 2005) have all been under intensive scientific investigations (at both field and laboratory scales) for understanding a variety of rock properties and their relations with flow and transport processes associated with geological disposal of nuclear waste. Clay/shale formations may be generally classified as indurated and plastic clays (Tsang et al., 2005). The latter (including Boom clay) is a softer material without high cohesion; its deformation is dominantly plastic. For both clay rocks, coupled thermal, hydrological, mechanical and chemical (THMC) processes are expected to have a significant impact on the long-term safety of a clay repository. For example, the excavation-damaged zone (EDZ) near repository tunnels can modify local permeability (resulting from induced fractures), potentially leading to less confinement capability (Tsang et al., 2005). Because of clay's swelling and shrinkage behavior (depending on whether the clay is in imbibition or drainage processes), fracture properties in the EDZ are quite dynamic and evolve over time as hydromechanical conditions change. To understand and model the coupled processes and their impact on repository performance is critical for the defensible performance assessment of a clay repository. Within the Natural Barrier System (NBS) group of the Used Fuel Disposition (UFD) Campaign at DOE's Office of Nuclear Energy, LBNL's research activities have focused on understanding and modeling such coupled processes. LBNL provided a report in this April on literature survey of studies on coupled processes in clay repositories and identification of technical issues and knowledge gaps (Tsang et al., 2010). This report will document other LBNL research activities within the natural system work package, including the development of constitutive relationships for elastic deformation of clay rock (Section 2), a THM modeling study (Section 3) and a THC modeling study (Section 4). The purpose of the THM and THC modeling studies is to demonstrate the current modeling capabilities in dealing with coupled processes in a potential clay repository. In Section 5, we discuss potential future R&D work based on the identified knowledge gaps. The linkage between these activities and related FEPs is presented in Section 6.

Liu, Hui-Hai; Rutqvist, Jonny; Zheng, Liange; Sonnenthal, Eric; Houseworth, Jim; Birkholzer, Jens

2010-08-31T23:59:59.000Z

326

Preliminary evaluation of alternative waste form solidification processes. Volume II. Evaluation of the processes  

Science Conference Proceedings (OSTI)

This Volume II presents engineering feasibility evaluations of the eleven processes for solidification of nuclear high-level liquid wastes (HHLW) described in Volume I of this report. Each evaluation was based in a systematic assessment of the process in respect to six principal evaluation criteria: complexity of process; state of development; safety; process requirements; development work required; and facility requirements. The principal criteria were further subdivided into a total of 22 subcriteria, each of which was assigned a weight. Each process was then assigned a figure of merit, on a scale of 1 to 10, for each of the subcriteria. A total rating was obtained for each process by summing the products of the subcriteria ratings and the subcriteria weights. The evaluations were based on the process descriptions presented in Volume I of this report, supplemented by information obtained from the literature, including publications by the originators of the various processes. Waste form properties were, in general, not evaluated. This document describes the approach which was taken, the developent and application of the rating criteria and subcriteria, and the evaluation results. A series of appendices set forth summary descriptions of the processes and the ratings, together with the complete numerical ratings assigned; two appendices present further technical details on the rating process.

Not Available

1980-08-01T23:59:59.000Z

327

Quality Assurance Program Plan (QAPP) Waste Management Project  

Science Conference Proceedings (OSTI)

The Waste Management Project (WMP) is committed to excellence in our work and to delivering quality products and services to our customers, protecting our employees and the public and to being good stewards of the environment. We will continually strive to understand customer requirements, perform services, and activities that meet or exceed customer expectations, and be cost-effective in our performance. The WMP maintains an environment that fosters continuous improvement in our processes, performance, safety and quality. The achievement of quality will require the total commitment of all WMP employees to our ethic that Quality, Health and Safety, and Regulatory Compliance must come before profits. The successful implementation of this policy and ethic requires a formal, documented management quality system to ensure quality standards are established and achieved in all activities. The following principles are the foundation of our quality system. Senior management will take full ownership of the quality system and will create an environment that ensures quality objectives are met, standards are clearly established, and performance is measured and evaluated. Line management will be responsible for quality system implementation. Each organization will adhere to all quality system requirements that apply to their function. Every employee will be responsible for their work quality, to work safely and for complying with the policies, procedures and instructions applicable to their activities. Quality will be addressed and verified during all phases of our work scope from proposal development through closeout including contracts or projects. Continuous quality improvement will be an ongoing process. Our quality ethic and these quality principles constantly guide our actions. We will meet our own quality expectations and exceed those of our customers with vigilance, commitment, teamwork, and persistence.

HORHOTA, M.J.

2000-12-21T23:59:59.000Z

328

Management Programs  

NLE Websites -- All DOE Office Websites (Extended Search)

3MS Environment and Waste Management Programs Environment and Waste Management Programs Environment and Waste Management Programs AN L-934 Surveillance of Site A and Plot M...

329

Management Programs  

NLE Websites -- All DOE Office Websites (Extended Search)

Environment and Waste Management Programs Environment and Waste Management Programs Environment and Waste Management Programs AN L-9213 Surveillance of Site A and Plot M Report...

330

Management Programs  

NLE Websites -- All DOE Office Websites (Extended Search)

r Environment and Waste Management Programs Environment and Waste Management Programs Environment and Waste Management Programs ANL-949 Surveillance of Site A and Plot M Report...

331

Scenarios of the TWRS low-level waste disposal program. Revision 1  

Science Conference Proceedings (OSTI)

As a result of past Department of Energy (DOE) weapons material production operations, Hanford now stores nuclear waste from processing facilities in underground tanks on the 200 area plateau. An agreement between the DOE, the Environmental Protection Agency (EPA), and the Washington state Department of Ecology (the Tri-Party Agreement, or TPA) establishes an enforceable schedule and a technical framework for recovering, processing, solidifying, and disposing of the Hanford tank wastes. The present plan includes retrieving the tank waste, pre-treating the waste to separate into low level and high level streams, and converting both streams to a glass waste form. The low level glass will represent by far the largest volume and lowest quantity of radioactivity (i.e., large volume of waste chemicals) of waste requiring disposal. The low level glass waste will be retrievably stored in sub-surface disposal vaults for several decades. If the low level disposal system proves to be acceptable, the disposal site will be closed with the low level waste in place. If, however, at some time the disposal system is found to be unacceptable, then the waste can be retrieved and dealt with in some other manner. WHC is planning to emplace the waste so that it is retrievable for up to 50 years after completion of the tank waste processing. Acceptability of disposal of the TWRS low level waste at Hanford depends on technical, cultural, and political considerations. The Performance Assessment is a major part of determining whether the proposed disposal action is technically defensible. A Performance Assessment estimates the possible future impact to humans and the environment for thousands of years into the future. In accordance with the TPA technical strategy, WHC plans to design a near-surface facility suitable for disposal of the glass waste.

NONE

1995-01-01T23:59:59.000Z

332

An evaluation of neutralization for processing sodium-bearing liquid waste  

SciTech Connect

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

333

Federal Energy Management Program: Portfolio-Based Planning Process for  

NLE Websites -- All DOE Office Websites (Extended Search)

Portfolio-Based Portfolio-Based Planning Process for Greenhouse Gas Mitigation to someone by E-mail Share Federal Energy Management Program: Portfolio-Based Planning Process for Greenhouse Gas Mitigation on Facebook Tweet about Federal Energy Management Program: Portfolio-Based Planning Process for Greenhouse Gas Mitigation on Twitter Bookmark Federal Energy Management Program: Portfolio-Based Planning Process for Greenhouse Gas Mitigation on Google Bookmark Federal Energy Management Program: Portfolio-Based Planning Process for Greenhouse Gas Mitigation on Delicious Rank Federal Energy Management Program: Portfolio-Based Planning Process for Greenhouse Gas Mitigation on Digg Find More places to share Federal Energy Management Program: Portfolio-Based Planning Process for Greenhouse Gas Mitigation on

334

BLENDING ANALYSIS FOR RADIOACTIVE SALT WASTE PROCESSING FACILITY  

SciTech Connect

Savannah River National Laboratory (SRNL) evaluated methods to mix and blend the contents of the blend tanks to ensure the contents are properly blended before they are transferred from the blend tank such as Tank 21 and Tank 24 to the Salt Waste Processing Facility (SWPF) feed tank. The tank contents consist of three forms: dissolved salt solution, other waste salt solutions, and sludge containing settled solids. This paper focuses on developing the computational model and estimating the operation time of submersible slurry pump when the tank contents are adequately blended prior to their transfer to the SWPF facility. A three-dimensional computational fluid dynamics approach was taken by using the full scale configuration of SRS Type-IV tank, Tank 21H. Major solid obstructions such as the tank wall boundary, the transfer pump column, and three slurry pump housings including one active and two inactive pumps were included in the mixing performance model. Basic flow pattern results predicted by the computational model were benchmarked against the SRNL test results and literature data. Tank 21 is a waste tank that is used to prepare batches of salt feed for SWPF. The salt feed must be a homogeneous solution satisfying the acceptance criterion of the solids entrainment during transfer operation. The work scope described here consists of two modeling areas. They are the steady state flow pattern calculations before the addition of acid solution for tank blending operation and the transient mixing analysis during miscible liquid blending operation. The transient blending calculations were performed by using the 95% homogeneity criterion for the entire liquid domain of the tank. The initial conditions for the entire modeling domain were based on the steady-state flow pattern results with zero second phase concentration. The performance model was also benchmarked against the SRNL test results and literature data.

Lee, S.

2012-05-10T23:59:59.000Z

335

TSD capacity model interface with waste reduction planning in the Environmental Restoration Program  

Science Conference Proceedings (OSTI)

This report provides a picture of how the integration of waste generation forecasting with treatment, storage, and disposal (TSD) capacity modeling interfaces with waste reduction planning in the Environmental Restoration Program. Background information is given for the major activities at the seven Martin Marietta Energy Systems, Inc., sites: (1) Oak Ridge National Laboratory; (2) Oak Ridge Y-12 Plant; (3) Oak Ridge K-25 Site; (4) Paducah Gaseous Diffusion Plant; (5) Portsmouth Gaseous Diffusion Plant; (6) Oak Ridge Associated Universities; and (7) the off-site contaminated areas near DOE facilities. A perspective is provided for strategies to achieve waste reduction, how waste generation forecasts rates were developed, and how those forecasted waste generation rates will be used in TSD capacity modeling. The generation forecasting in combination with TSD modeling allows development of quantifiable goals and subsequent waste reduction. 2 figs.

Phifer, B.E. Jr.; Grumski, J.T.

1991-01-01T23:59:59.000Z

336

Proceedings of the Third Annual Information Meeting DOE Low-Level Waste-Management Program  

SciTech Connect

The Third Annual Participants Information Meeting of the Low-Level Waste Management Program was held in New Orleans, Louisiana, November 4-6, 1981 The specific purpose was to bring together appropriate representatives of industry, USNRC, program management, participating field offices, and contractors to: (1) exchange information and analyze program needs, and (2) involve participants in planning, developing and implementing technology for low-level waste management. One hundred seven registrants participated in the meeting. Presentation and workshop findings are included in these proceedings under the following headings: low-level waste activities; waste treatment; shallow land burial; remedial action; greater confinement; ORNL reports; panel workshops; and summary. Forty-six papers have been abstracted and indexed for the data base.

Large, D.E.; Lowrie, R.S.; Stratton, L.E.; Jacobs, D.G. (comps.)

1981-12-01T23:59:59.000Z

337

Hanford Site waste minimization and pollution prevention awareness program plan. Revision 1  

SciTech Connect

The Hanford Site WMin/P2 program is an organized, comprehensive, and continual effort to systematically reduce the quantity and toxicity of hazardous, radioactive, mixed, and sanitary wastes; conserve resources; and prevent or minimize pollutant releases to all environmental media from all Site activities. The Hanford Site WMin/P2 program plan reflects national and DOE waste minimization and pollution prevention goals and policies, and represents an ongoing effort to make WMin/P2 part of the Site operating philosophy. In accordance with these policies, a hierarchical approach to environmental management has been adopted and is applied to all types of polluting and waste generating activities. Pollution prevention and waste minimization through source reduction are first priority in the Hanford WMin/P2 program, followed by environmentally safe recycling. Treatment to reduce the quantity, toxicity, and/or mobility will be considered only when prevention or recycling are not possible or practical. Environmentally safe disposal is the last option.

Not Available

1994-05-01T23:59:59.000Z

338

West Valley demonstration project: alternative processes for solidifying the high-level wastes  

SciTech Connect

In 1980, the US Department of Energy (DOE) established the West Valley Solidification Project as the result of legislation passed by the US Congress. The purpose of this project was to carry out a high level nuclear waste management demonstration project at the Western New York Nuclear Service Center in West Valley, New York. The DOE authorized the Pacific Northwest Laboratory (PNL), which is operated by Battelle Memorial Institute, to assess alternative processes for treatment and solidification of the WNYNSC high-level wastes. The Process Alternatives Study is the suject of this report. Two pretreatment approaches and several waste form processes were selected for evaluation in this study. The two waste treatment approaches were the salt/sludge separation process and the combined waste process. Both terminal and interim waste form processes were studied.

Holton, L.K.; Larson, D.E.; Partain, W.L.; Treat, R.L.

1981-10-01T23:59:59.000Z

339

EA-0915: Waste Tank Safety Program Hanford Site, Richland, Washington  

Energy.gov (U.S. Department of Energy (DOE))

This EA evaluates the environmental impacts of the proposal to resolve waste tank safety issues at the Hanford Site near the City of Richland, Washington, and to reduce the risks associated with...

340

Idaho Chemical Processing Plant training program  

SciTech Connect

Objectives, regulations and requirements, training methods, certification and recertification, progression and incentives, and coverage of the ICPP operator training program are discussed in detail. (LK)

1975-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste processing program" 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

RECOMMENDED FRIT COMPOSITION FOR INITIAL SLUDGE BATCH 5 PROCESSING AT THE DEFENSE WASTE PROCESSING FACILITY  

SciTech Connect

The Savannah River National Laboratory (SRNL) Frit Development Team recommends that the Defense Waste Processing Facility (DWPF) utilize Frit 418 for initial processing of high level waste (HLW) Sludge Batch 5 (SB5). The extended SB5 preparation time and need for DWPF feed have necessitated the use of a frit that is already included on the DWPF procurement specification. Frit 418 has been used previously in vitrification of Sludge Batches 3 and 4. Paper study assessments predict that Frit 418 will form an acceptable glass when combined with SB5 over a range of waste loadings (WLs), typically 30-41% based on nominal projected SB5 compositions. Frit 418 has a relatively high degree of robustness with regard to variation in the projected SB5 composition, particularly when the Na{sub 2}O concentration is varied. The acceptability (chemical durability) and model applicability of the Frit 418-SB5 system will be verified experimentally through a variability study, to be documented separately. Frit 418 has not been designed to provide an optimal melt rate with SB5, but is recommended for initial processing of SB5 until experimental testing to optimize a frit composition for melt rate can be completed. Melt rate performance can not be predicted at this time and must be determined experimentally. Note that melt rate testing may either identify an improved frit for SB5 processing (one which produces an acceptable glass at a faster rate than Frit 418) or confirm that Frit 418 is the best option.

Fox, K; Tommy Edwards, T; David Peeler, D

2008-06-25T23:59:59.000Z

342

FRIT OPTIMIZATION FOR SLUDGE BATCH PROCESSING AT THE DEFENSE WASTE PROCESSING FACILITY  

SciTech Connect

The Savannah River National Laboratory (SRNL) Frit Development Team recommends that the Defense Waste Processing Facility (DWPF) utilize Frit 418 for initial processing of high level waste (HLW) Sludge Batch 5 (SB5). The extended SB5 preparation time and need for DWPF feed have necessitated the use of a frit that is already included on the DWPF procurement specification. Frit 418 has been used previously in vitrification of Sludge Batches 3 and 4. Paper study assessments predict that Frit 418 will form an acceptable glass when combined with SB5 over a range of waste loadings (WLs), typically 30-41% based on nominal projected SB5 compositions. Frit 418 has a relatively high degree of robustness with regard to variation in the projected SB5 composition, particularly when the Na{sub 2}O concentration is varied. The acceptability (chemical durability) and model applicability of the Frit 418-SB5 system will be verified experimentally through a variability study, to be documented separately. Frit 418 has not been designed to provide an optimal melt rate with SB5, but is recommended for initial processing of SB5 until experimental testing to optimize a frit composition for melt rate can be completed. Melt rate performance can not be predicted at this time and must be determined experimentally. Note that melt rate testing may either identify an improved frit for SB5 processing (one which produces an acceptable glass at a faster rate than Frit 418) or confirm that Frit 418 is the best option.

Fox, K.

2009-01-28T23:59:59.000Z

343

Overview of Waste Processing & Recycling of Nonferrous Metals in ...  

Science Conference Proceedings (OSTI)

Selective Recovery of Gold from E-wastes by Using Cellulosic Wastes · Stabilization of Chromium-Based Slags with FeS2 and FeSO4 · Sulphide Precipitation ...

344

Recovery of Iron from Waste Slag of Pyrite Processing Using ...  

Science Conference Proceedings (OSTI)

Selective Recovery of Gold from E-wastes by Using Cellulosic Wastes · Stabilization of Chromium-Based Slags with FeS2 and FeSO4 · Sulphide Precipitation ...

345

Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Import Statement, Richland, Washington - Summary  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Link to Main Report Link to Main Report RESPONSIBLE AGENCY: COVER SHEET 1 2 3 4 5 6 7 8 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 U.S. Department of Energy, Richland Operations Office TITLE: Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement, Richland, Benton County, Washington (DOE/EIS-0286D2) CONTACT: For further information on this document, write or call: Mr. Michael S. Collins HSW EIS Document Manager Richland Operations Office U.S. Department of Energy, A6-38 P.O. Box 550 Richland, Washington 99352-0550 Telephone: (800) 426-4914 Fax: (509) 372-1926 Email: hsweis@rl.gov For further information on the Department's National Environmental Policy Act process,

346

Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Import Statement, Richland, Washington  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

COVER SHEET 1 COVER SHEET 1 U.S. Department of Energy, Richland Operations Office 2 3 TITLE: 4 Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact 5 Statement, Richland, Benton County, Washington (DOE/EIS-0286D2) 6 7 CONTACT: 8 For further information on this document, write or call: Mr. Michael S. Collins HSW EIS Document Manager Richland Operations Office U.S. Department of Energy, A6-38 P.O. Box 550 Richland, Washington 99352-0550 Telephone: (800) 426-4914 Fax: (509) 372-1926 Email: hsweis@rl.gov For further information on the Department's National Environmental Policy Act process, contact: Ms. Carol M. Borgstrom, Director Office of NEPA Policy and Compliance, EH-42 U.S. Department of Energy 1000 Independence Avenue, S.W.

347

Final Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement Richland, Washington  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

COVER SHEET COVER SHEET U.S. Department of Energy, Richland Operations Office TITLE: Final Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement, Richland, Benton County, Washington (DOE/EIS-0286F) CONTACT: For further information on this document, write or call: Mr. Michael S. Collins HSW EIS Document Manager Richland Operations Office U.S. Department of Energy, A6-38 P.O. Box 550 Richland, Washington 99352-0550 Telephone: (509) 376-6536 Fax: (509) 372-1926 Email: hsweis@rl.gov For further information on the Department's National Environmental Policy Act (NEPA) process, contact: Ms. Carol M. Borgstrom, Director Office of NEPA Policy and Compliance, EH-42 U.S. Department of Energy 1000 Independence Avenue, S.W.

348

Preliminary waste acceptance criteria for the ICPP spent fuel and waste management technology development program  

SciTech Connect

The purpose of this document is to identify requirements to be met by the Producer/Shipper of Spent Nuclear Fuel/High-LeveL Waste SNF/HLW in order for DOE to be able to accept the packaged materials. This includes defining both standard and nonstandard waste forms.

Taylor, L.L.; Shikashio, R.

1993-09-01T23:59:59.000Z

349

Defense Transuranic Waste Program. Transuranic waste transportation assessment and guidance report  

SciTech Connect

The Transportation Assessment and Guidance Report (TAGR) is designed to provide DOE-managed defense sites with guidance and citable analyses addressing National Environmental Policy Act (NEPA) requirements for qualifying and transporting transuranic (TRU) wastes to the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico.

1985-08-01T23:59:59.000Z

350

Composition and process for the encapsulation and stabilization of radioactive hazardous and mixed wastes  

DOE Patents (OSTI)

The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining substantially simultaneously dry waste powder, a non-biodegradable thermoplastic polymer and an anhydrous additive in an extruder to form a homogeneous molten matrix. The molten matrix may be directed in a ``clean`` polyethylene liner, allowed to cool, thus forming a monolithic waste form which provides a multibarrier to the dispersion of wastes into the environment. 2 figs.

Kalb, P.D.; Colombo, P.

1997-07-15T23:59:59.000Z

351

Composition and process for the encapsulation and stabilization of radioactive, hazardous and mixed wastes  

DOE Patents (OSTI)

The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining substantially simultaneously dry waste powder, a non-biodegradable thermoplastic polymer and an anhydrous additive in an extruder to form a homogeneous molten matrix. The molten matrix may be directed in a ``clean`` polyethylene liner, allowed to cool, thus forming a monolithic waste form which provides a multibarrier to the dispersion of wastes into the environment. 2 figs.

Kalb, P.D.; Colombo, P.

1998-03-24T23:59:59.000Z

352

Composition and process for the encapsulation and stabilization of radioactive, hazardous and mixed wastes  

DOE Patents (OSTI)

The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining substantially simultaneously dry waste powder, a non-biodegradable thermoplastic polymer and an anhydrous additive in an extruder to form a homogenous molten matrix. The molten matrix may be directed in a "clean" polyethylene liner, allowed to cool, thus forming a monolithic waste form which provides a multibarrier to the dispersion of wastes into the environment.

Kalb, Paul D. (Wading River, NY); Colombo, Peter (Patchogue, NY)

1999-07-20T23:59:59.000Z

353

Composition and process for the encapsulation and stabilization of radioactive hazardous and mixed wastes  

DOE Patents (OSTI)

The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining substantially simultaneously dry waste powder, a non-biodegradable thermoplastic polymer and an anhydrous additive in an extruder to form a homogenous molten matrix. The molten matrix may be directed in a "clean" polyethylene liner, allowed to cool, thus forming a monolithic waste form which provides a multibarrier to the dispersion of wastes into the environment.

Kalb, Paul D. (21 Barnes Road, Wading River, NY 11792); Colombo, Peter (44 N. Pinelake Dr., Patchogue, NY 11772)

1997-01-01T23:59:59.000Z

354

Composition and process for the encapsulation and stabilization of radioactive, hazardous and mixed wastes  

DOE Patents (OSTI)

The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining substantially simultaneously dry waste powder, a non-biodegradable thermoplastic polymer and an anhydrous additive in an extruder to form a homogenous molten matrix. The molten matrix may be directed in a "clean" polyethylene liner, allowed to cool, thus forming a monolithic waste form which provides a multibarrier to the dispersion of wastes into the environment.

Kalb, Paul D. (Wading River, NY); Colombo, Peter (Patchogue, NY)

1998-03-24T23:59:59.000Z

355

Composition and process for the encapsulation and stabilization of radioactive, hazardous and mixed wastes  

DOE Patents (OSTI)

The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining substantially simultaneously dry waste powder, a non-biodegradable thermoplastic polymer and an anhydrous additive in an extruder to form a homogeneous molten matrix. The molten matrix may be directed in a clean'' polyethylene liner, allowed to cool, thus forming a monolithic waste form which provides a multibarrier to the dispersion of wastes into the environment. 2 figs.

Kalb, P.D.; Colombo, P.

1999-07-20T23:59:59.000Z

356

Dynamic modeling and multivariable control of organic Rankine cycles in waste heat utilizing processes  

Science Conference Proceedings (OSTI)

In this paper, the dynamics of organic Rankine cycles (ORCs) in waste heat utilizing processes is investigated, and the physical model of a 100 kW waste heat utilizing process is established. In order to achieve both transient performance and steady-state ... Keywords: Linear quadratic regulator, Organic Rankine cycles, Process control

Jianhua Zhang; Wenfang Zhang; Guolian Hou; Fang Fang

2012-09-01T23:59:59.000Z

357

ANL Technical Support Program for DOE Environmental Restoration and Waste Management; Annual report, October 1992--September 1993  

SciTech Connect

This report is an overview of the progress during FY 1993 for the Technical Support Program that is part of the ANL Technology Support Activity for DOE Environmental Restoration and Waste Management (EM). The purpose is to evaluate, before hot start-up of the Defense Waste Processing Facility (DWPF) and the West Valley Demonstration Project (WVDP), factors that are anticipated to affect glass reaction in an unsaturated environment typical of what may be expected for the candidate Yucca Mountain repository site. Specific goals for the testing program include the following: reviewing and evaluating available data on parameters that will be important in establishing the long-term performance of glass in a repository environment; performing tests to further quantify the effects of important variables where there are deficiencies in the available data; and initiating long-term tests to determine glass performance under a range of conditions applicable to repository disposal.

Bates, J.K.; Bourcier, W.L.; Bradley, C.R. [and others

1994-06-01T23:59:59.000Z

358

ANL Technical Support Program for DOE Environmental Restoration and Waste Management. Annual report, October 1990--September 1991  

SciTech Connect

This report provides an overview of progress during FY 1991 for the Technical Support Program that is part of the ANL Technology Support Activity for DOE, Environmental Restoration and Waste Management (EM). The purpose is to evaluate, before hot start-up of the Defenses Waste Processing Facility (DWPF) and the West Valley Demonstration Project (WVDP), factors that are likely to affect glass reaction in an unsaturated environment typical of what may be expected for the candidate Yucca Mountain repository site. Specific goals for the testing program include the following: (1) to review and evaluate available information on parameters that will be important in establishing the long-term performance of glass in a repository environment; (2) to perform testing to further quantify the effects of important variables where there are deficiencies in the available data; and (3) to initiate long-term testing that will bound glass performance under a range of conditions applicable to repository disposal.

Bates, J.K.; Bradley, C.R.; Buck, E.C.; Cunnane, J.C.; Dietz, N.L.; Ebert, W.L.; Emery, J.W.; Feng, X.; Gerding, T.J.; Gong, M.; Hoh, J.C.; Mazer, J.J.; Wronkiewicz, D.J. [Argonne National Lab., IL (United States); Bourcier, W.L.; Morgan, L.E.; Nielsen, J.K.; Steward, S.A. [Lawrence Livermore National Lab., CA (United States); Ewing, R.C.; Wang, L.M. [New Mexico Univ., Albuquerque, NM (United States); Han, W.T.; Tomozawa, M. [Rensselaer Polytechnic Inst., Troy, MI (United States)

1992-03-01T23:59:59.000Z

359

Waste receiving and processing plant control system; system design description  

Science Conference Proceedings (OSTI)

The Plant Control System (PCS) is a heterogeneous computer system composed of numerous sub-systems. The PCS represents every major computer system that is used to support operation of the Waste Receiving and Processing (WRAP) facility. This document, the System Design Description (PCS SDD), includes several chapters and appendices. Each chapter is devoted to a separate PCS sub-system. Typically, each chapter includes an overview description of the system, a list of associated documents related to operation of that system, and a detailed description of relevant system features. Each appendice provides configuration information for selected PCS sub-systems. The appendices are designed as separate sections to assist in maintaining this document due to frequent changes in system configurations. This document is intended to serve as the primary reference for configuration of PCS computer systems. The use of this document is further described in the WRAP System Configuration Management Plan, WMH-350, Section 4.1.

LANE, M.P.

1999-02-24T23:59:59.000Z

360

Process for preparing lubricating oil from used waste lubricating oil  

DOE Patents (OSTI)

A re-refining process is described by which high-quality finished lubricating oils are prepared from used waste lubricating and crankcase oils. The used oils are stripped of water and low-boiling contaminants by vacuum distillation and then dissolved in a solvent of 1-butanol, 2-propanol and methylethyl ketone, which precipitates a sludge containing most of the solid and liquid contaminants, unspent additives, and oxidation products present in the used oil. After separating the purified oil-solvent mixture from the sludge and recovering the solvent for recycling, the purified oil is preferably fractional vacuum-distilled, forming lubricating oil distillate fractions which are then decolorized and deodorized to prepare blending stocks. The blending stocks are blended to obtain a lubricating oil base of appropriate viscosity before being mixed with an appropriate additive package to form the finished lubricating oil product.

Whisman, Marvin L. (Bartlesville, OK); Reynolds, James W. (Bartlesville, OK); Goetzinger, John W. (Bartlesville, OK); Cotton, Faye O. (Bartlesville, OK)

1978-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste processing program" 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 PowerPoint - 1-07 Mason DOE EM Waste Processing Technology...  

NLE Websites -- All DOE Office Websites (Extended Search)

plants: Studsvik Processing Facility: Ion exchange resins (45" diameter FBSR) DOE Idaho Integrated Waste Treatment Unit: SBW treatment (48" diameter FBSR) DOE...

362

Nuclear criticality safety analysis summary report: The S-area defense waste processing facility  

SciTech Connect

The S-Area Defense Waste Processing Facility (DWPF) can process all of the high level radioactive wastes currently stored at the Savannah River Site with negligible risk of nuclear criticality. The characteristics which make the DWPF critically safe are: (1) abundance of neutron absorbers in the waste feeds; (2) and low concentration of fissionable material. This report documents the criticality safety arguments for the S-Area DWPF process as required by DOE orders to characterize and to justify the low potential for criticality. It documents that the nature of the waste feeds and the nature of the DWPF process chemistry preclude criticality.

Ha, B.C.

1994-10-21T23:59:59.000Z

363

National Waste Terminal Storage Program: potenial problems in the waste transportation system  

SciTech Connect

Potential problems are identified which may impact the planning, organization, and operation of nuclear waste transportation systems serving federal repositories. These system-level problems have the potential of seriously interfering with the overall OWI Transportation/Logistics Study objective of having a viable nuclear waste transportation system in 1985. This report includes recommended action and priority judgments to address these problems and minimize their impact. The potential problems identified as most important have consequences which may impact the overall state of future preparedness for transporting nuclear waste. Other important concerns relate to the imposition of unnecessarily severe and costly restrictions on nuclear waste transportation, public and carrier acceptance, and the involvement of interested parties in planning and decision-making. The major recommendation of this report is that the planning and development of the waste transportation system should be controlled by a central planning activity which anticipates the impact of uncertainties and undesirable events.

DeSteese, J.G.; Rhoads, R.E.

1977-12-01T23:59:59.000Z

364

International Best Practices for Pre-Processing and Co-Processing Municipal Solid Waste and Sewage Sludge in the Cement Industry  

E-Print Network (OSTI)

uniformity. Shredding of mixed waste to about 10 centimetersand untreated mixed municipal waste. GTZ/Holcim (2006) givesCEMBUREAU 2009). Mixed municipal waste must be pre-processed

Hasanbeigi, Ali

2013-01-01T23:59:59.000Z

365

International Best Practices for Pre-Processing and Co-Processing Municipal Solid Waste and Sewage Sludge in the Cement Industry  

E-Print Network (OSTI)

n.d. “Co-Processing of Waste and Energy Efficiency By CementAnnual North American Waste-to-Energy Conference NAWTEC17,2009. Stantec, 2011. Waste to Energy: a Technical Review of

Hasanbeigi, Ali

2013-01-01T23:59:59.000Z

366

GRR/Section 18 - Waste and Hazardous Material Assessment Process | Open  

Open Energy Info (EERE)

- Waste and Hazardous Material Assessment Process - Waste and Hazardous Material Assessment Process < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18 - Waste and Hazardous Material Assessment Process 18 - WasteAndHazardousMaterialAssessmentProcess.pdf Click to View Fullscreen Contact Agencies Environmental Protection Agency Regulations & Policies RCRA CERCLA 40 CFR 261 Triggers None specified Click "Edit With Form" above to add content 18 - WasteAndHazardousMaterialAssessmentProcess.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative The use of underground and above ground storage tanks, discovery of waste

367

GRR/Section 18-AK-c - Waste Disposal Permit Process | Open Energy  

Open Energy Info (EERE)

AK-c - Waste Disposal Permit Process AK-c - Waste Disposal Permit Process < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-AK-c - Waste Disposal Permit Process 18AKC - WasteDisposalPermitProcess (1).pdf Click to View Fullscreen Contact Agencies Alaska Department of Environmental Conservation Regulations & Policies AS 46.03.110 Waste Disposal Permit Regulations 18 AAC 60.200 et seq Triggers None specified Click "Edit With Form" above to add content 18AKC - WasteDisposalPermitProcess (1).pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative The Alaska Department of Environmental Conservation (DEC) is responsible

368

GRR/Section 18-OR-b - Hazardous Waste Permit Process | Open Energy  

Open Energy Info (EERE)

OR-b - Hazardous Waste Permit Process OR-b - Hazardous Waste Permit Process < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-OR-b - Hazardous Waste Permit Process 18ORBHazardousWastePermitProcess (1).pdf Click to View Fullscreen Contact Agencies United States Environmental Protection Agency Oregon Department of Environmental Quality Oregon Public Health Division Oregon Public Utility Commission Oregon Department of Fish and Wildlife Oregon Water Resources Department Regulations & Policies OAR 340-105: Management Facility Permits OAR 340-120: Hazardous Waste Management ORS 466: Storage, Treatment, and Disposal Triggers None specified Click "Edit With Form" above to add content 18ORBHazardousWastePermitProcess (1).pdf

369

Separating and Stabilizing Phosphate from High-Level Radioactive Waste: Process Development and Spectroscopic Monitoring  

SciTech Connect

Removing phosphate from alkaline high-level waste sludges at the Department of Energy's Hanford Site in Washington State is necessary to increase the waste loading in the borosilicate glass waste form that will be used to immobilize the highly radioactive fraction of these wastes. We are developing a process which first leaches phosphate from the high-level waste solids with aqueous sodium hydroxide, and then isolates the phosphate by precipitation with calcium oxide. Tests with actual tank waste confirmed that this process is an effective method of phosphate removal from the sludge and offers an additional option for managing the phosphorus in the Hanford tank waste solids. The presence of vibrationally active species, such as nitrate and phosphate ions, in the tank waste processing streams makes the phosphate removal process an ideal candidate for monitoring by Raman or infrared spectroscopic means. As a proof-of-principle demonstration, Raman and Fourier transform infrared (FTIR) spectra were acquired for all phases during a test of the process with actual tank waste. Quantitative determination of phosphate, nitrate, and sulfate in the liquid phases was achieved by Raman spectroscopy, demonstrating the applicability of Raman spectroscopy for the monitoring of these species in the tank waste process streams.

Lumetta, Gregg J.; Braley, Jenifer C.; Peterson, James M.; Bryan, Samuel A.; Levitskaia, Tatiana G.

2012-05-09T23:59:59.000Z

370

Transuranic Waste Program Framework Agreement - December Deliverable July 2012  

SciTech Connect

Framework agreement deliverables are: (1) 'DOE/NNSA commits to complete removal of all non-cemented above-ground EM Legacy TRU and newly generated TRU currently-stored at Area G as of October 1, 2011, by no later than June 30, 2014. This inventory of above-ground TRU is defined as 3706 cubic meters of material.' (2) 'DOE commits to the complete removal of all newly generated TRU received in Area G during FY 2012 and 2013 by no later than December 31, 2014.' (3) 'Based on projected funding profiles, DOE/NNSA will develop by December 31, 2012, a schedule, including pacing milestones, for disposition of the below-ground TRU requiring retrieval at Area G.' Objectives are to: (1) restore the 'Core Team' to develop the December, 2012 deliverable; (2) obtain agreement on the strategy for below ground water disposition; and (3) establish timeline for completion of the deliverable. Below Grade Waste Strategy is to: (1) Perform an evaluation on below grade waste currently considered retrievable TRU; (2) Only commit to retrieve waste that must be retrieved; (3) Develop the Deliverable including Pacing Milestones based on planned commitments; (4) Align all Regulatory Documents for Consistency; and (5) answer these 3 primary questions, is the waste TRU; is the waste retrievable, can retrieval cause more harm than benefit?

Jones, Patricia [Los Alamos National Laboratory

2012-07-19T23:59:59.000Z

371

Zone Freezing Study for Pyrochemical Process Waste Minimization  

Science Conference Proceedings (OSTI)

Pyroprocessing technology is a non-aqueous separation process for treatment of used nuclear fuel. At the heart of pyroprocessing lies the electrorefiner, which electrochemically dissolves uranium from the used fuel at the anode and deposits it onto a cathode. During this operation, sodium, transuranics, and fission product chlorides accumulate in the electrolyte salt (LiCl-KCl). These contaminates change the characteristics of the salt overtime and as a result, large volumes of contaminated salt are being removed, reprocessed and stored as radioactive waste. To reduce the storage volumes and improve recycling process for cost minimization, a salt purification method called zone freezing has been proposed at Korea Atomic Energy Research Institute (KAERI). Zone freezing is melt crystallization process similar to the vertical Bridgeman method. In this process, the eutectic salt is slowly cooled axially from top to bottom. As solidification occurs, the fission products are rejected from the solid interface and forced into the liquid phase. The resulting product is a grown crystal with the bulk of the fission products near the bottom of the salt ingot, where they can be easily be sectioned and removed. Despite successful feasibility report from KAERI on this process, there were many unexplored parameters to help understanding and improving its operational routines. Thus, this becomes the main motivation of this proposed study. The majority of this work has been focused on the CsCl-LiCl-KCl ternary salt. CeCl3-LiCl-KCl was also investigated to check whether or not this process is feasible for the trivalent species—surrogate for rare-earths and transuranics. For the main part of the work, several parameters were varied, they are: (1) the retort advancement rate—1.8, 3.2, and 5.0 mm/hr, (2) the crucible lid configurations—lid versus no-lid, (3) the amount or size of mixture—50 and 400 g, (4) the composition of CsCl in the salt—1, 3, and 5 wt%, and (5) the temperature differences between the high and low furnace zones—200 and 300 ?C. During each experiment, the temperatures at selected locations around the crucible were measured and recorded to provide temperature profiles. Following each experiment, samples were collected and elemental analysis was done to determine the composition of iii the salt. Several models—non-mixed, well-mixed, Favier, and hybrid—were explored to describe the zone freezing process. For CsCl-LiCl-KCl system, experimental results indicate that through this process up to 90% of the used salt can be recycled, effectively reducing waste volume by a factor of ten. The optimal configuration was found to be a 5.0 mm/hr rate with a lid configuration and a ?T of 200°C. The larger 400 g mixtures had recycle percentages similar to the 50 g mixtures; however, the throughput per time was greater for the 400 g case. As a result, the 400 g case is recommended. For the CeCl3-LiCl-KCl system, the result implies that it is possible to use this process to separate the rare-earth and transuranics chlorides. Different models were applied to only CsCl ternary system. The best fit model was the hybrid model as a result of a solute transport transition from non- mixed to well-mixed throughout the growing process.

Ammon Williams

2012-05-01T23:59:59.000Z

372

Characterization of decontamination and decommissioning wastes expected from the major processing facilities in the 200 Areas  

SciTech Connect

This study was intended to characterize and estimate the amounts of equipment and other materials that are candidates for removal and subsequent processing in a solid waste facility when the major processing and handling facilities in the 200 Areas of the Hanford Site are decontaminated and decommissioned. The facilities in this study were selected based on processing history and on the magnitude of the estimated decommissioning cost cited in the Surplus Facilities Program Plan; Fiscal Year 1993 (Winship and Hughes 1992). The facilities chosen for this study include B Plant (221-B), T Plant (221-T), U Plant (221-U), the Uranium Trioxide (UO{sub 3}) Plant (224-U and 224-UA), the Reduction Oxidation (REDOX) or S Plant (202-S), the Plutonium Concentration Facility for B Plant (224-B), and the Concentration Facility for the Plutonium Finishing Plant (PFP) and REDOX (233-S). This information is required to support planning activities for current and future solid waste treatment, storage, and disposal operations and facilities.

Amato, L.C.; Franklin, J.D.; Hyre, R.A.; Lowy, R.M.; Millar, J.S.; Pottmeyer, J.A. [Los Alamos Technical Associates, Kennewick, WA (United States); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (United States)

1994-08-01T23:59:59.000Z

373

Meta-interpretation of recursive list-processing programs  

Science Conference Proceedings (OSTI)

Presented Is an implemented program understanding system called CAN. CAN relies on a meta-interpretation process which brings to light two new concepts concerning meta-interpretation of recursive programs: vicious circles and constructive induction. ... Keywords: conceptual representations, constructive induction, meta-interpretation, program understanding, propagation, unification, vicious circle

Daniel Goossens

1979-08-01T23:59:59.000Z

374

New desorption process treats refinery K and F wastes in demo trial  

SciTech Connect

A new desorption process for treating refinery wastes has been proven in pilot demonstrations at Amoco Oil Co.'s Texas City, Tex., refinery. The process -- Waste-Tech Services Inc.'s desorption and recovery unit (DRU) -- treats petroleum-contaminated refinery wastes and recovers oil and water suitable for recycling to the refinery. The DRU meets Resource Conservation and Recovery Act (RCRA) recycle exemptions and produces solids that satisfy US Environmental Protection Agency (EPA) land disposal restrictions (LDRs). This paper discusses RCRA wastes, the process, the demonstration unit, operating conditions, and analyses of semivolatiles, volatiles, leachable metals, and recovered oil and water.

Rasmussen, G.P. (Waste-Tech Services Inc., Golden, CO (United States))

1994-01-10T23:59:59.000Z

375

Waste Heat Recovery from Refrigeration in a Meat Processing Facility  

E-Print Network (OSTI)

A case study is reviewed on a heat recovery system installed in a meat processing facility to preheat water for the plant hot water supply. The system utilizes waste superheat from the facility's 1,350-ton ammonia refrigeration system. The heat recovery system consists of a shell and tube heat exchanger (16"? x 14'0") installed in the compressor hot gas discharge line. Water is recirculated from a 23,000-gallon tempered water storage tank to the heat exchanger by a circulating pump at the rate of 100 gallons per minute. All make-up water to the plant hot water system is supplied from this tempered water storage tank, which is maintained at a constant filled level. Tests to determine the actual rate of heat recovery were conducted from October 3, 1979 to October 12, 1979, disclosing an average usage of 147,000 gallons of hot water daily. These tests illustrated a varied heat recovery of from 0.5 to 1.0 million BTU per hour. The deviations were the result of both changing refrigeration demands and compressor operating modes. An average of 16 million BTU per day was realized, resulting in reduced boiler fuel costs of $30,000 annually, based on the present $.80 per gallon #2 fuel oil price. At the total installed cost of $79,000, including test instrumentation, the project was found to be economically viable. The study has demonstrated the technical and economic feasibility of refrigeration waste heat recovery as a positive energy conservation strategy which has broad applications in industry and commerce.

Murphy, W. T.; Woods, B. E.; Gerdes, J. E.

1980-01-01T23:59:59.000Z

376

Followup of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process Systems Hazards Analysis Activity Review, March 2013  

NLE Websites -- All DOE Office Websites (Extended Search)

HSS Independent Activity Report - HSS Independent Activity Report - Rev. 0 Report Number: HIAR-WTP-2013-03-18 Site: Hanford Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Follow-up of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity Review Dates of Activity : 03/18/13 - 03/21/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff observed a limited portion of the restart of the Hazard Analysis (HA) for the Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) Melter Process (LMP) System. The primary purpose of this HSS field activity, on March 18-21, 2013, was to observe and understand the revised approach

377

Followup of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process Systems Hazards Analysis Activity Review, March 2013  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

HSS Independent Activity Report - HSS Independent Activity Report - Rev. 0 Report Number: HIAR-WTP-2013-03-18 Site: Hanford Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Follow-up of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity Review Dates of Activity : 03/18/13 - 03/21/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff observed a limited portion of the restart of the Hazard Analysis (HA) for the Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) Melter Process (LMP) System. The primary purpose of this HSS field activity, on March 18-21, 2013, was to observe and understand the revised approach

378

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

379

Waste Receiving and Processing Facility Module 1 Data Management System Software Requirements Specification  

Science Conference Proceedings (OSTI)

This document provides the software requirements for Waste Receiving and Processing (WRAP) Module 1 Data Management System (DMS). The DMS is one of the plant computer systems for the new WRAP 1 facility (Project W-026). The DMS will collect, store and report data required to certify the low level waste (LLW) and transuranic (TRU) waste items processed at WRAP 1 as acceptable for shipment, storage, or disposal.

Brann, E.C. II

1994-09-09T23:59:59.000Z

380

Atmospheric fluidized bed combustion of municipal solid waste: test program results  

DOE Green Energy (OSTI)

Air classified municipal solid waste (MSW) was fired in an atmospheric fluidized bed combustor at low excess air to simulate boiler conditions. The 7 ft/sup 2/ combustor at Combustion Power Company's energy laboratory in Menlo Park, CA, incorporates water tubes for heat extraction and recycles elutriated particles to the bed. System operation was stable while firing processed MSW for the duration of a 300-h test. Low excess air, low exhaust gas emissions, and constant bed temperature demonstrated feasibility of steam generation from fluidized bed combustion of MSW. During the 300-h test, combustion efficiency averaged 99%. Excess air was typically 44% while an average bed temperature of 1400/sup 0/F and an average superficial gas velocity of 4.6 fps were maintained. Typical exhaust emission levels were 30 ppM SO/sub 2/, 160 ppM NO/sub x/, 200 ppM CO, and 25 ppM hydrocarbons. No agglomeration of bed material or detrimental change in fluidization properties was experienced. A conceptual design study of a full scale plant to be located at Stanford University was based on process conditions from the 300-h test. The plant would produce 250,000 lb/hr steam at the maximum firing rate of 1000 tons per day (TPD) processed MSW. The average 800 TPD firing rate would utilize approximately 1200 TPD raw MSW from surrounding communities. The Stanford Solid Waste energy Program was aimed at development of a MSW-fired fluidized bed boiler and cogeneration plant to supply most of the energy needs of Stanford University.

Preuit, L C; Wilson, K B

1980-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste processing program" 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

Electrochemical processing of nitrate waste solutions. Phase 2, Final report  

SciTech Connect

The second phase of research performed at The Electrosynthesis Co., Inc. has demonstrated the successful removal of nitrite and nitrate from a synthetic effluent stream via a direct electrochemical reduction at a cathode. It was shown that direct reduction occurs at good current efficiencies in 1,000 hour studies. The membrane separation process is not readily achievable for the removal of nitrites and nitrates due to poor current efficiencies and membrane stability problems. A direct reduction process was studied at various cathode materials in a flow cell using the complete synthetic mix. Lead was found to be the cathode material of choice, displaying good current efficiencies and stability in short and long term tests under conditions of high temperature and high current density. Several anode materials were studied in both undivided and divided cell configurations. A divided cell configuration was preferable because it would prevent re-oxidation of nitrite by the anode. The technical objective of eliminating electrode fouling and solids formation was achieved although anode materials which had demonstrated good stability in short term divided cell tests corroded in 1,000 hour experiments. The cause for corrosion is thought to be F{sup {minus}} ions from the synthetic mix migrating across the cation exchange membrane and forming HF in the acid anolyte. Other possibilities for anode materials were explored. A membrane separation process was investigated which employs an anion and cation exchange membrane to remove nitrite and nitrate, recovering caustic and nitric acid. Present research has shown poor current efficiencies for nitrite and nitrate transport across the anion exchange membrane due to co-migration of hydroxide anions. Precipitates form within the anion exchange membranes which would eventually result in the failure of the membranes. Electrochemical processing offers a highly promising and viable method for the treatment of nitrate waste solutions.

Genders, D.; Weinberg, N.; Hartsough, D. [Electrosynthesis Co., Inc., Cheektowaga, NY (US)

1992-10-07T23:59:59.000Z

382

DEVELOPMENT PROGRAM FOR PU-238 AQUEOUS RECOVERY PROCESS  

SciTech Connect

Aqueous processing is necessary for the removal of impurities from {sup 238}Pu dioxide ({sup 238}PuO{sub 2}) fuel due to unacceptable levels of {sup 234}U and other non-actinide impurities in the scrap fuel. Impurities at levels above General Purpose Heat Source (GPHS) fuel specifications may impair the performance.of the heat sources. Efforts at Los Alamos have focused on developing the bench scale methodology for the aqueous process steps which includes comminution, dissolution, ion exchange, precipitation, and calcination. Recently, work has been performed to qualify the bench scale methodology, to show that the developed process produces pure {sup 238}PuO{sub 2} meeting GPHS fuel specifications. In addition, this work has enabled us to determine how waste volumes may be minimized during full-scale processing. Results of process qualification for the bench scale aqueous recovery operation and waste minimization efforts are presented.

M. PANSOY-HJELVIK; M. REIMUS; ET AL

2000-10-01T23:59:59.000Z

383

Adequacy of a Small Quantity Site RH-TRU Waste Program in Meeting Proposed WIPP Characterization Objectives  

SciTech Connect

The first remote-handled transuranic (RH-TRU) waste is expected to be permanently disposed of at the Waste Isolation Pilot Plant (WIPP) during Fiscal Year (FY) 2003. The first RH-TRU waste shipments are scheduled from the Battelle Columbus Laboratories (BCL) to WIPP in order to facilitate compliance with BCL Decommissioning Project (BCLDP) milestones. Milestones requiring RH-TRU waste containerization and removal from the site by 2004 in order to meet a 2006 site closure goal, established by Congress in the Defense Facilities Closure Projects account, necessitated the establishment and implementation of a site-specific program to direct the packaging of BCLDP RH-TRU waste prior to the finalization of WIPP RH-TRU waste characterization requirements. The program was designed to collect waste data, including audio and videotape records of waste packaging, such that upon completion of waste packaging, comprehensive data records exist from which compliance with final WIPP RH-TRU waste characterization requirements can be demonstrated. With the BCLDP data records generated to date and the development by the U.S. Department of Energy (DOE)-Carlsbad Field Office (CBFO) of preliminary documents proposing the WIPP RH-TRU waste characterization program, it is possible to evaluate the adequacy of the BCLDP program with respect to meeting proposed characterization objectives. The BCLDP characterization program uses primarily acceptable knowledge (AK) and visual examination (VE) during waste packaging to characterize RH-TRU waste. These methods are used to estimate physical waste parameters, including weight percentages of metals, cellulosics, plastics, and rubber in the waste, and to determine the absence of prohibited items, including free liquids. AK combined with computer modeling is used to estimate radiological waste parameters, including total activity on a waste container basis, for the majority of BCLDP RH-TRU waste. AK combined with direct analysis is used to characterize radiological parameters for the small populations of the RH-TRU waste generated by the BCLDP. All characterization based on AK is verified. Per its design for comprehensive waste data collection, the BCLDP characterization program using AK and waste packaging procedures, including VE during packaging, meets the proposed WIPP RH-TRU waste characterization objectives. The conservative program design implemented generates certification data that will be adequate to meet any additional program requirements that may be imposed by the CBFO.

Biedscheid, J.; Stahl, S.; Devarakonda, M.; Peters, K.; Eide, J.

2002-02-26T23:59:59.000Z

384

Accident Fault Trees for Defense Waste Processing Facility  

Science Conference Proceedings (OSTI)

The purpose of this report is to document fault tree analyses which have been completed for the Defense Waste Processing Facility (DWPF) safety analysis. Logic models for equipment failures and human error combinations that could lead to flammable gas explosions in various process tanks, or failure of critical support systems were developed for internal initiating events and for earthquakes. These fault trees provide frequency estimates for support systems failures and accidents that could lead to radioactive and hazardous chemical releases both on-site and off-site. Top event frequency results from these fault trees will be used in further APET analyses to calculate accident risk associated with DWPF facility operations. This report lists and explains important underlying assumptions, provides references for failure data sources, and briefly describes the fault tree method used. Specific commitments from DWPF to provide new procedural/administrative controls or system design changes are listed in the ''Facility Commitments'' section. The purpose of the ''Assumptions'' section is to clarify the basis for fault tree modeling, and is not necessarily a list of items required to be protected by Technical Safety Requirements (TSRs).

Sarrack, A.G.

1999-06-22T23:59:59.000Z

385

SRS - Programs - Nonproliferation Programs  

NLE Websites -- All DOE Office Websites (Extended Search)

3/2012 3/2012 SEARCH GO spacer SRS Home Nonproliferation Programs In the crucial field of nuclear nonproliferation, SRS employee contributions helped to advance all three of the planned plutonium disposition facilities at the Savannah River Site: the Pit Disassembly and Conversion Facility (PDCF); Waste Solidification Building (WSB); and the Mixed Oxide (MOX) Fuel Fabrication Facility. A $345 million project, the WSB will process liquid waste from the MOX facility. After material is processed at the WSB, transuranic waste will be packaged and sent to the Waste Isolation Pilot Plant in New Mexico, and low-level waste will be packaged and sent to onsite or commercial off-site low-level waste disposal facilities. The mixed oxide fuel fabrication facility will be a major component in the United States' program to dispose of excess weapons grade plutonium.

386

Environmental management 1994. Progress and plans of the environmental restoration and waste management program  

SciTech Connect

The Department of Energy currently faces one of the largest environmental challenges in the world. The Department`s Environmental Restoration and Waste Management program is responsible for identifying and reducing risks and managing waste at 137 sites in 34 States and territories where nuclear energy or weapons research and production resulted in radioactive, hazardous, and mixed waste contamination. The number of sites continues to grow as facilities are transferred to be cleaned up and closed down. The program`s main challenge is to balance technical and financial realities with the public`s expectations and develop a strategy that enables the Department to meet its commitments to the American people. This document provides a closer look at what is being done around the country. Included are detailed discussions of the largest sites in the region, followed by site activities organized by state, and a summary of activities at FUSRAP and UMTRA sites in the region.

Not Available

1994-02-01T23:59:59.000Z

387

Chapter 38 Hazardous Waste Permitting Process (Kentucky) | Open...  

Open Energy Info (EERE)

Policy Contact Contact Name Anthony Hatton (director) Department Department for Environmental Protection Division Division of Waste Management Address 200 Fair Oaks L.,...

388

Metals Mobilization During E-Waste Bioleaching Process: Effect of ...  

Science Conference Proceedings (OSTI)

A Study on Waste Packaging Containers Generated by Household in Taiwan ... Mullites Bodies Produced From the Kaolin Residue Using Microwave Energy.

389

Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Oversight Assessment of Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project May 2011 January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project

390

Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project  

NLE Websites -- All DOE Office Websites (Extended Search)

Oversight Assessment of Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project May 2011 January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project

391

Program Geothm: A thermodynamic process program for geothermal power plant cycles  

DOE Green Energy (OSTI)

Program GEOTHM is a thermodynamic process program now under development for the LBL Geothermal Energy Program. To date, the program development has centered upon the modeling of working fluid properties, developing thermodynamic process models, and modeling the design performance of geothermal power plants. When the program is completed, it will be able to optimize a power plant or refrigeration plant for minimum cost power or refrigeration. Furthermore, operation of the thermodynamic cycles at off design conditions will be able to be simulated. Program GEOTHM is currently able to calculate several types of geothermal power cycles using a wide variety of working fluids.

Green, M.A.; Pines, H.S.

1974-10-01T23:59:59.000Z

392

CHEMICAL PROCESS RESEARCH AND DEVELOPMENT PROGRAM  

E-Print Network (OSTI)

the fermentation and distillation processes have beensteam production. The distillation energy requirement islow energy costs to distillation column pressure. A second

Authors, Various

2013-01-01T23:59:59.000Z

393

GRR/Section 18-AK-b - Hazardous Waste Permit Process | Open Energy  

Open Energy Info (EERE)

8-AK-b - Hazardous Waste Permit Process 8-AK-b - Hazardous Waste Permit Process < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-AK-b - Hazardous Waste Permit Process 18AKB - HazardousWastePermitProcess (1).pdf Click to View Fullscreen Contact Agencies Alaska Department of Environmental Conservation United States Environmental Protection Agency Regulations & Policies AS 46.03.302 18 AAC 60.020 Triggers None specified Click "Edit With Form" above to add content 18AKB - HazardousWastePermitProcess (1).pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative The Alaska Department of Environmental Conservation defers to the federal

394

GLASS-CERAMICS IN A COLD-CRUCIBLE MELTER : THE OPTIMUM COMBINATION FOR GREATER WASTE PROCESSING EFFICIENCY  

SciTech Connect

Improving the efficiency of nuclear waste immobilization is constantly desired by all nuclear waste management programs world-wide. For high-level and other waste to be vitrified in traditional ceramic Joule-heated melters operated at temperatures up to 1150 C, process flexibilities including waste loadings are often restricted by this temperature limit as well as the need to consider wasteform corrosion of refractory linings and electrodes. New melter technologies, such as the cold-crucible melter (CCM), enable processing up to significantly higher temperatures free of many of the limitations of conventional melters. Higher processing temperatures open up the way for wider composition and processing envelopes to be considered for the vitrification process, including the possibility for higher waste loadings. In many instances the presence of crystals in the final cooled wasteform is not considered desirable within presently existing glass specifications. For some feed compositions in creased waste loadings can lead to the formation of large amounts of crystals, and thus to a significant departure from the ''glass'' state. Nevertheless it is recognized that, in general, increasing the acceptable volume fractions of crystals in the glass offers the best opportunity to increase waste loading, all other factors being equal. In addition, the deliberate promotion of specific crystalline phases by design may enhance the quality of the wasteform, for example by partitioning a long-lived radionuclide into a very stable crystalline phase, or by depleting the glass in detrimental elements. In order to explore the potential improvements by harnessing the higher achievable processing temperatures and immunity to refractory corrosion available with the cold-crucible melter, and after promising indications for synroc-based matrices, it was decided to investigate the feasibility of designing and producing via melting new high temperature ''glass-ceramic'' wasteforms for high level was te immobilization. The INEEL calcines were selected as example feed compositions. These calcines have a wide range of problematic compositions. They either have high amounts of crystal-forming components, and/or components that lead to corrosive melts, and for good measure, the components in some waste types are quite refractory for vitrification as well. The recent DOE High-Level Waste Melter Review Report concluded that, for the INEEL calcine wastes in particular, the CCM could have sufficient advantages over the Joule-heated ceramic melter to justify its evaluation for direct vitrification of these wastes. Based on the extensive ceramic design experience of ANSTO, in collaboration with the CEA and COGEMA for a CCM implementation, a preliminary set of waste forms has been developed that immobilize long-lived waste actinides into highly chemically durable crystalline phases by design, using refractory crystal-forming components already in the wastes to advantage, while at the same tim e maintaining a very good overall leach resistance for the glass-ceramics even after ''canister centerline cooling'' (CCC) heat treatments. This paper presents the results of a 50 kg technological scale test in the CCM of a glass-ceramic formulation for the average Bin Set 2 formulation, at a conservative waste loading of 50%.

DAY, R.A.; FERENCZY, J.; DRABAREK, E.; ADVOCAT, T.; FILLET, C.; LACOMBE, J.; LADIRAT, C.; VEYER, C.; QUANG, R. DO; THOMASSON, J.

2003-02-27T23:59:59.000Z

395

Using Waste Heat for External Processes (English/Chinese) (Fact Sheet)  

SciTech Connect

Chinese translation of the Using Waste Heat for External Processes fact sheet. Provides suggestions on how to use waste heat in industrial applications. The temperature of exhaust gases from fuel-fired industrial processes depends mainly on the process temperature and the waste heat recovery method. Figure 1 shows the heat lost in exhaust gases at various exhaust gas temperatures and percentages of excess air. Energy from gases exhausted from higher temperature processes (primary processes) can be recovered and used for lower temperature processes (secondary processes). One example is to generate steam using waste heat boilers for the fluid heaters used in petroleum crude processing. In addition, many companies install heat exchangers on the exhaust stacks of furnaces and ovens to produce hot water or to generate hot air for space heating.

Not Available

2011-10-01T23:59:59.000Z

396

Cold End Inserts for Process Gas Waste Heat Boilers Air Products, operates hydrogen production plants, which utilize large waste heat boilers (WHB)  

E-Print Network (OSTI)

Cold End Inserts for Process Gas Waste Heat Boilers Overview Air Products, operates hydrogen production plants, which utilize large waste heat boilers (WHB) to cool process syngas. The gas enters satisfies all 3 design criteria. · Correlations relating our experimental results to a waste heat boiler

Demirel, Melik C.

397

Waste Isolation Pilot Plant Medical Screening Program, Phase I: Needs Assessment  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Waste Isolation Pilot Plant Waste Isolation Pilot Plant Medical Screening Program Phase I: Needs Assessment Presented to the Office of Worker Screening and Compensation Support, Office of Health, Safety, and Security U.S. Department of Energy Prepared by Queens College, City University of New York United Steelworkers Original Draft: August 22, 2011 Updated Version: May 1, 2012 Table of Contents Summary.............................................................................3 I. Background on the Former Worker Program................................4 II. History of the WIPP Facility......................................................4 III. Scope of this Report.................................................................7 IV. Exposure Characterization........................................................8

398

Process and material that encapsulates solid hazardous waste  

DOE Patents (OSTI)

A method of encapsulating mixed waste in which a thermoplastic polymer having a melting temperature less than about 150.degree. C. and sulfur and mixed waste are mixed at an elevated temperature not greater than about 200.degree. C. and mixed for a time sufficient to intimately mix the constituents, and then cooled to a solid. The resulting solid is also disclosed.

O' Brien, Michael H. (Idaho Falls, ID); Erickson, Arnold W. (Idaho Falls, ID)

1999-01-01T23:59:59.000Z

399

Recycling of Wastes Generated during the Steelmaking Process  

Science Conference Proceedings (OSTI)

These are wastes with considerable production and limited applications, therefore this work studied the recovery of these wastes into ... Clayey Ceramic Incorporated with Powder from the Sintering Plant of a Steel-Making Industry ... Influence of Fly Ash and Fluorgypsum on Hydration Heat and Mortar Strength of Cement.

400

Process and material that encapsulates solid hazardous waste  

DOE Patents (OSTI)

A method is described for encapsulating mixed waste in which a thermoplastic polymer having a melting temperature less than about 150 C and sulfur and mixed waste are mixed at an elevated temperature not greater than about 200 C and mixed for a time sufficient to intimately mix the constituents, and then cooled to a solid. The resulting solid is also disclosed.

O' Brien, Michael H.; Erickson, Arnold W.

1997-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste processing program" 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

Optional Tour Program - TMS  

Science Conference Proceedings (OSTI)

TMS Logo. About the 1996 International Symposium on Extraction and Processing for the Treatment and Minimization of Wastes: Optional Tour Program  ...

402

Energy Technical Assistance: Industrial Processes Program  

E-Print Network (OSTI)

The Energy Technical Assistance Division of Texas Engineering Extension Service (TEEX) has implemented an energy conservation program to assist small industry in using energy more efficiently. This full time service, an outgrowth of the Texas A&M University College of Engineering activities, is available through support of Texas Energy and Natural Resources Advisory Council. Engineers with industry and consulting experience are located in Arlington and Houston TEEX offices.

McClure, J. D.

1980-01-01T23:59:59.000Z

403

Glovebox design requirements for molten salt oxidation processing of transuranic waste  

SciTech Connect

This paper presents an overview of potential technologies for stabilization of {sup 238}Pu-contaminated combustible waste. Molten salt oxidation (MSO) provides a method for removing greater than 99.999% of the organic matrix from combustible waste. Implementation of MSO processing at the Los Alamos National Laboratory (LANL) Plutonium Facility will eliminate the combustible matrix from {sup 238}Pu-contaminated waste and consequently reduce the cost of TRU waste disposal operations at LANL. The glovebox design requirements for unit operations including size reduction and MSO processing will be presented.

Ramsey, K.B.; Acosta, S.V. [Los Alamos National Lab., NM (United States); Wernly, K.D. [Molten Salt Oxidation Corp., Bensalem, PA (United States)

1998-12-31T23:59:59.000Z

404

Thermal Processing of Wastes - III (Eaf and Iron & Steel Plant Wastes)  

Science Conference Proceedings (OSTI)

... OF WASTE MATERIALS IN A FERROCHROME INDUSTRY: S. A. Platias, MIRTEC S. A., Research Division, Á Industrial Area, 38500 Volos, Greece. 2:50 pm.

405

Nuclear Solid Waste Processing Design at the Idaho Spent Fuels Facility  

Science Conference Proceedings (OSTI)

A spent nuclear fuels (SNF) repackaging and storage facility was designed for the Idaho National Engineering and Environmental Laboratory (INEEL), with nuclear solid waste processing capability. Nuclear solid waste included contaminated or potentially contaminated spent fuel containers, associated hardware, machinery parts, light bulbs, tools, PPE, rags, swabs, tarps, weld rod, and HEPA filters. Design of the nuclear solid waste processing facilities included consideration of contractual, regulatory, ALARA (as low as reasonably achievable) exposure, economic, logistical, and space availability requirements. The design also included non-attended transfer methods between the fuel packaging area (FPA) (hot cell) and the waste processing area. A monitoring system was designed for use within the FPA of the facility, to pre-screen the most potentially contaminated fuel canister waste materials, according to contact- or non-contact-handled capability. Fuel canister waste materials which are not able to be contact-handled after attempted decontamination will be processed remotely and packaged within the FPA. Noncontact- handled materials processing includes size-reduction, as required to fit into INEEL permitted containers which will provide sufficient additional shielding to allow contact handling within the waste areas of the facility. The current design, which satisfied all of the requirements, employs mostly simple equipment and requires minimal use of customized components. The waste processing operation also minimizes operator exposure and operator attendance for equipment maintenance. Recently, discussions with the INEEL indicate that large canister waste materials can possibly be shipped to the burial facility without size-reduction. New waste containers would have to be designed to meet the drop tests required for transportation packages. The SNF waste processing facilities could then be highly simplified, resulting in capital equipment cost savings, operational time savings, and significantly improved ALARA exposure.

Dippre, M. A.

2003-02-25T23:59:59.000Z

406

Federal Energy Management Program: Product Designation Process  

NLE Websites -- All DOE Office Websites (Extended Search)

Designation Process Training Available Graphic of the eTraining logo Energy-Efficient Federal Purchasing: This intermediate FEMP eTraining course offers hands-on learning on...

407

CHEMICAL PROCESS RESEARCH AND DEVELOPMENT PROGRAM  

E-Print Network (OSTI)

U.S. Dept. of Energy. Chemical Marketing Reporter, JanuaryUniv. of Calif. Dept. of Chemical Engineering (March 1977).Ergun et aL, "Analysis of Chemical Coal Cleaning Processes,"

Authors, Various

2013-01-01T23:59:59.000Z

408

Adoption Process | Building Energy Codes Program  

NLE Websites -- All DOE Office Websites (Extended Search)

Adoption Process Energy codes are adopted at the state and local jurisdiction levels and, in most cases, are part of a broader set of codes addressing building, fire, electrical...

409

Solvent extraction and recovery of the transuranic elements from waste solutions using the TRUEX process  

SciTech Connect

High-level liquid waste is produced during the processing of irradiated nuclear fuel by the PUREX process. In some cases the treatment of metallurgical scrap to recover the plutonium values also generates a nitric acid waste solution. Both waste solutions contain sufficient concentrations of transuranic elements (mostly /sup 241/Am) to require handling and disposal as a TRU waste. This paper describes a recently developed solvent extraction/recovery process called TRUEX (transuranium extraction) which is designed to reduce the TRU concentration in nitric waste solutions to <100 nCi/g of disposed form (1,2). (In the USA, non-TRU waste is defined as <100 nCi of TRU/g of disposed form.) The process utilizes PUREX process solvent (TBP in a normal paraffinic hydrocarbon or carbon tetrachloride) modified by a small concentration of octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (abbrev. CMPO). The presence of CMPO enables the modified PUREX process solvent to extract trivalent actinides as well as tetra- and hexavalent actinides. A major feature of the TRUEX process is that is is applicable to waste solutions containing a wide range of nitric acid, salt, and fission product concentrations and at the same time is very compatible with existing liquid-liquid extraction technology as usually practiced in a fuel reprocessing plant. To date the process has been tested on two different types of synthetic waste solutions. The first solution is a typical high-level nitric acid waste and the second a typical waste solution generated in metallurgical scrap processing. Results are discussed. 4 refs., 1 fig., 4 tabs.

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

1985-01-01T23:59:59.000Z