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1

TSA waste stream and final waste form composition  

SciTech Connect

A final vitrified waste form composition, based upon the chemical compositions of the input waste streams, is recommended for the transuranic-contaminated waste stored at the Transuranic Storage Area of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The quantities of waste are large with a considerable uncertainty in the distribution of various waste materials. It is therefore impractical to mix the input waste streams into an ``average`` transuranic-contaminated waste. As a result, waste stream input to a melter could vary widely in composition, with the potential of affecting the composition and properties of the final waste form. This work examines the extent of the variation in the input waste streams, as well as the final waste form under conditions of adding different amounts of soil. Five prominent Rocky Flats Plant 740 waste streams are considered, as well as nonspecial metals and the ``average`` transuranic-contaminated waste streams. The metals waste stream is the most extreme variation and results indicate that if an average of approximately 60 wt% of the mixture is soil, the final waste form will be predominantly silica, alumina, alkaline earth oxides, and iron oxide. This composition will have consistent properties in the final waste form, including high leach resistance, irrespective of the variation in waste stream. For other waste streams, much less or no soil could be required to yield a leach resistant waste form but with varying properties.

Grandy, J.D.; Eddy, T.L.; Anderson, G.L.

1993-01-01T23:59:59.000Z

2

Nuclear Utility Mixed Waste Stream Characterization Study  

Science Conference Proceedings (OSTI)

This report presents industry experience at nuclear utilities in characterizing the hazardous component of potential mixed waste streams. It identifies key considerations for characterizing mixed waste; provides background information, including actual sample results, on the majority of plant processes with a potential to generate mixed waste; and presents a methodology for characterizing mixed waste.

1994-12-31T23:59:59.000Z

3

New Waste Calcining Facility (NWCF) Waste Streams  

SciTech Connect

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

K. E. Archibald

1999-08-01T23:59:59.000Z

4

History of Rocky Flats waste streams  

SciTech Connect

An analysis of the waste streams at Rocky Flats was done to provide information for the Waste Certification program. This program has involved studying the types and amounts of retrievable transuranic (TRU) waste from Rocky Flats that is stored at the Idaho National Engineering Laboratory (INEL). The information can be used to estimate the types and amounts of waste that will need to be permanently stored in the Waste Isolation Pilot Plant (WIPP). The study covered mostly the eight-year period from June 1971 to June 1979. The types, amounts, and plutonium content of TRU waste and the areas or operations responsible for generating the waste are summarized in this waste stream history report. From the period studied, a total of 24,546,153 lbs of waste containing 211,148 g of plutonium currently occupies 709,497 cu ft of storage space at INEL.

Luckett, L.L.; Dickman, A.A.; Wells, C.R.; Vickery, D.J.

1982-03-10T23:59:59.000Z

5

Waste streams for algae cultivation.  

E-Print Network (OSTI)

??ALDIGA, short for “Algae from Waste for Combined Biodiesel and Biogas Pro-duction”, aims to develop a concept for a closed circulation of resources in pro-ducing… (more)

Kautto, Antti

2011-01-01T23:59:59.000Z

6

Operational Waste Stream Assumption for TSLCC Estimates  

Science Conference Proceedings (OSTI)

This document provides the background and basis for the operational waste stream used in the 2000 Total System Life Cycle Cost (TSLCC) estimate for the Civilian Radioactive Waste Management System (CRWMS). This document has been developed in accordance with its Development Plan (CRWMS M&O 2000a), and AP-3.11Q, ''Technical Reports''.

S. Gillespie

2000-09-01T23:59:59.000Z

7

Baseline Glass Development for Combined Fission Products Waste Streams  

SciTech Connect

Borosilicate glass was selected as the baseline technology for immobilization of the Cs/Sr/Ba/Rb (Cs), lanthanide (Ln) and transition metal fission product (TM) waste steams as part of a cost benefit analysis study.[1] Vitrification of the combined waste streams have several advantages, minimization of the number of waste forms, a proven technology, and similarity to waste forms currently accepted for repository disposal. A joint study was undertaken by Pacific Northwest National Laboratory (PNNL) and Savannah River National Laboratory (SRNL) to develop acceptable glasses for the combined Cs + Ln + TM waste streams (Option 1) and Cs + Ln combined waste streams (Option 2) generated by the AFCI UREX+ set of processes. This study is aimed to develop baseline glasses for both combined waste stream options and identify key waste components and their impact on waste loading. The elemental compositions of the four-corners study were used along with the available separations data to determine the effect of burnup, decay, and separations variability on estimated waste stream compositions.[2-5] Two different components/scenarios were identified that could limit waste loading of the combined Cs + LN + TM waste streams, where as the combined Cs + LN waste stream has no single component that is perceived to limit waste loading. Combined Cs + LN waste stream in a glass waste form will most likely be limited by heat due to the high activity of Cs and Sr isotopes.

Crum, Jarrod V.; Billings, Amanda Y.; Lang, Jesse B.; Marra, James C.; Rodriguez, Carmen P.; Ryan, Joseph V.; Vienna, John D.

2009-06-29T23:59:59.000Z

8

Actinide removal from nitric acid waste streams  

SciTech Connect

Actinide separations research at the Rocky Flats Plant (RFP) has found ways to significantly improve plutonium secondary recovery and americium removal from nitric acid waste streams generated by plutonium purification operations. Capacity and breakthrough studies show anion exchange with Dowex 1x4 (50 to 100 mesh) to be superior for secondary recovery of plutonium. Extraction chromatography with TOPO(tri-n-octyl-phosphine oxide) on XAD-4 removes the final traces of plutonium, including hydrolytic polymer. Partial neutralization and solid supported liquid membrane transfer removes americium for sorption on discardable inorganic ion exchangers, potentially allowing for non-TRU waste disposal.

Muscatello, A.C.; Navratil, J.D.

1986-01-01T23:59:59.000Z

9

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

10

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

SciTech Connect

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

1992-04-01T23:59:59.000Z

11

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

SciTech Connect

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

COZZI, ALEX

2004-02-18T23:59:59.000Z

12

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

SciTech Connect

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

COZZI, ALEX

2004-02-18T23:59:59.000Z

13

Microsoft Word - INL Waste Stream Cleared for Shipment to WIPP...  

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

Idaho National Laboratory Waste Stream Cleared For Shipment to WIPP CARLSBAD, N.M., December 12, 2006 - The U.S. Department of Energy (DOE) has authorized the Idaho National...

14

Glass Ceramic Waste Forms for Combined CS+LN+TM Fission Products Waste Streams  

SciTech Connect

In this study, glass ceramics were explored as an alternative waste form for glass, the current baseline, to be used for immobilizing alkaline/alkaline earth + lanthanide (CS+LN) or CS+LN+transition metal (TM) fission-product waste streams generated by a uranium extraction (UREX+) aqueous separations type process. Results from past work on a glass waste form for the combined CS+LN waste streams showed that as waste loading increased, large fractions of crystalline phases precipitated upon slow cooling.[1] The crystalline phases had no noticeable impact on the waste form performance by the 7-day product consistency test (PCT). These results point towards the development of a glass ceramic waste form for treating CS+LN or CS+LN+TM combined waste streams. Three main benefits for exploring glass ceramics are: (1) Glass ceramics offer increased solubility of troublesome components in crystalline phases as compared to glass, leading to increased waste loading; (2) The crystalline network formed in the glass ceramic results in higher heat tolerance than glass; and (3) These glass ceramics are designed to be processed by the same melter technology as the current baseline glass waste form. It will only require adding controlled canister cooling for crystallization into a glass ceramic waste form. Highly annealed waste form (essentially crack free) with up to 50X lower surface area than a typical High-Level Waste (HLW) glass canister. Lower surface area translates directly into increased durability. This was the first full year of exploring glass ceramics for the Option 1 and 2 combined waste stream options. This work has shown that dramatic increases in waste loading are achievable by designing a glass ceramic waste form as an alternative to glass. Table S1 shows the upper limits for heat, waste loading (based on solubility), and the decay time needed before treatment can occur for glass and glass ceramic waste forms. The improvements are significant for both combined waste stream options in terms of waste loading and/or decay time required before treatment. For Option 1, glass ceramics show an increase in waste loading of 15 mass % and reduction in decay time of 24 years. Decay times of {approx}50 years or longer are close to the expected age of the fuel that will be reprocessed when the modified open or closed fuel cycle is expected to be put into action. Option 2 shows a 2x to 2.5x increase in waste loading with decay times of only 45 years. Note that for Option 2 glass, the required decay time before treatment is only 35 years because of the waste loading limits related to the solubility of MoO{sub 3} in glass. If glass was evaluated for similar waste loadings as those achieved in Option 2 glass ceramics, the decay time would be significantly longer than 45 years. These glass ceramics are not optimized, but already they show the potential to dramatically reduce the amount of waste generated while still utilizing the proven processing technology used for glass production.

Crum, Jarrod V.; Turo, Laura A.; Riley, Brian J.; Tang, Ming; Kossoy, Anna; Sickafus, Kurt E.

2010-09-23T23:59:59.000Z

15

Hanford Site Hazardous waste determination report for transuranic debris waste streams NPFPDL2A  

SciTech Connect

This hazardous waste determination report (Report) describes the process and information used on the Hanford Site to determine that waste stream number NPFPDLZA, consisting of 30 containers of contact-handled transuranic debris waste, is not hazardous waste regulated by the Resource Conservation and Recovery Act (RCRA) or the New Mexico Hazardous Waste Act. For a waste to be hazardous under these statutes, the waste either must be specifically listed as a hazardous waste, or exhibit one or more of the characteristics of a hazardous waste, Le., ignitability, corrosivity, reactivity, or toxicity. Waste stream NPFPDLZA was generated, packaged, and placed into storage between 1993 and 1997. Extensive knowledge of the waste generating process, facility operational history, and administrative controls and operating procedures in effect at the time of generation, supported the initial nonhazardous waste determination. Because of the extent and reliability of information pertaining to this waste type, and the total volume of waste in the debris matrix parameter category, the Hanford Site is focusing initial efforts on this and similar waste streams for the first shipment to the Waste Isolation Pilot Plant (WIPP). RCRA regulations authorize hazardous waste determinations to be made either by using approved sampling and analysis methods or by applying knowledge of the waste in light of the materials or the process(es) used. This latter approach typically is referred to as process knowledge. The Transuranic Waste Characterization Quality Assurance Program Plan (CAO-94-1010) for WIPP refers to acceptable knowledge in essentially the same terms; acceptable knowledge as used throughout this Report is synonymous with the term process knowledge. The 30 containers addressed in this Report were characterized by the following methods: Acceptable knowledge; Nondestructive examination using real-time radiography; Visual examination; and Headspace gas sampling and analysis. The initial nonhazardous waste determination was based solely on acceptable knowledge. Relevant administrative documents and operating methods in effect at the time of waste generation were reviewed, generator waste profiles and certifications were examined, and personnel interviews were conducted. The acceptable knowledge information and supporting data were further evaluated based on the results of nondestructive examination, visual examination, and container headspace gas analysis. In all cases, the physical examination processes supported the initial nonhazardous waste determination, and in effect served to validate and finalize that determination. Sections 2.0 through 5.0 of this Report describe in more detail the actions taken and conclusions reached with respect to this nonhazardous waste determination, The hazardous waste determination process described in this Report fully satisfies the requirements of 40 CFR 261, and the Memorandum of Agreement (MOA-June 16, 1999) signed by the U.S. Department of Energy (DOE) and the New Mexico Environment Department pertaining to the exchange of waste stream information.

WINTERHALDER, J.A.

1999-09-29T23:59:59.000Z

16

An Economic Assessment of Market-Based Approaches to Regulating the Municipal Solid Waste Stream  

E-Print Network (OSTI)

Total (lbs) Total recycle compost Community Characteristicsdiscards percent diverted compost Waste/HH/Day after PAYTof recycled waste streams, compost, and possibly from energy

Menell, Peter S.

2004-01-01T23:59:59.000Z

17

High-temperature waste-heat-stream selection and characterization  

Science Conference Proceedings (OSTI)

Four types of industrial high-temperature, corrosive waste heat streams are selected that could yield significant energy savings if improved heat recovery systems were available. These waste heat streams are the flue gases from steel soaking pits, steel reheat furnaces, aluminum remelt furnaces, and glass melting furnaces. Available information on the temperature, pressure, flow, and composition of these flue gases is given. Also reviewed are analyses of corrosion products and fouling deposits resulting from the interaction of these flue gases with materials in flues and heat recovery systems.

Wikoff, P.M.; Wiggins, D.J.; Tallman, R.L.; Forkel, C.E.

1983-08-01T23:59:59.000Z

18

Hazardous Waste Code Determination for First/Second-Stage Sludge Waste Stream (IDCs 001, 002, 800)  

Science Conference Proceedings (OSTI)

This document, Hazardous Waste Code Determination for the First/Second-Stage Sludge Waste Stream, summarizes the efforts performed at the Idaho National Engineering and Environmental Laboratory (INEEL) to make a hazardous waste code determination on Item Description Codes (IDCs) 001, 002, and 800 drums. This characterization effort included a thorough review of acceptable knowledge (AK), physical characterization, waste form sampling, chemical analyses, and headspace gas data. This effort included an assessment of pre-Waste Analysis Plan (WAP) solidified sampling and analysis data (referred to as preliminary data). Seventy-five First/Second-Stage Sludge Drums, provided in Table 1-1, have been subjected to core sampling and analysis using the requirements defined in the Quality Assurance Program Plan (QAPP). Based on WAP defined statistical reduction, of preliminary data, a sample size of five was calculated. That is, five additional drums should be core sampled and analyzed. A total of seven drums were sampled, analyzed, and validated in compliance with the WAP criteria. The pre-WAP data (taken under the QAPP) correlated very well with the WAP compliant drum data. As a result, no additional sampling is required. Based upon the information summarized in this document, an accurate hazardous waste determination has been made for the First/Second-Stage Sludge Waste Stream.

Arbon, R.E.

2001-01-31T23:59:59.000Z

19

Future radioactive liquid waste streams study  

SciTech Connect

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

Rey, A.S.

1993-11-01T23:59:59.000Z

20

Disposal Activities and the Unique Waste Streams at the Nevada National Security Site (NNSS)  

SciTech Connect

This slide show documents waste disposal at the Nevada National Security Site. Topics covered include: radionuclide requirements for waste disposal; approved performance assessment (PA) for depleted uranium disposal; requirements; program approval; the Waste Acceptance Review Panel (WARP); description of the Radioactive Waste Acceptance Program (RWAP); facility evaluation; recent program accomplishments, nuclear facility safety changes; higher-activity waste stream disposal; large volume bulk waste streams.

Arnold, P.

2012-10-31T23:59:59.000Z

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

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

Science Conference Proceedings (OSTI)

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

Ogle, R.B. [comp.

1994-03-01T23:59:59.000Z

22

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

Science Conference Proceedings (OSTI)

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

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

1997-08-21T23:59:59.000Z

23

Alternate Fuels: Is Your Waste Stream a Fuel Source?  

E-Print Network (OSTI)

Before the year 2000, more than one quarter of U.S. businesses will be firing Alternate Fuels in their boiler systems. And, the trend toward using Process Gases, Flammable Liquids, and Volatile Organic Compounds (VOC's), to supplement fossil fuels, will be considered a key element of the management strategy for industrial power plants. The increase in interest in Alternate Fuels and demand for proven Alternate Fuel technology is being driven by three factors -* The requirement of U.S. firms to compete in a global market. * The improvements in Alternate Fuel technologies. * The increasing federal regulations encompassing more types of waste streams. This paper will provide an overview of the types of waste utilized as fuel sources in packaged boilers and the technology available to successfully handle these waste streams.

Coerper, P.

1992-04-01T23:59:59.000Z

24

Mixed and Low-Level Waste Treatment Facility Project. Appendix B, Waste stream engineering files: Part 2, Low-level waste streams  

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. This report documents those studies so the project can continue with an evaluation of programmatic options, system tradeoff studies, and the conceptual design phase of the project. This report, appendix B, comprises the engineering design files for this project study. The engineering design files document each waste steam, its characteristics, and identified treatment strategies.

1992-04-01T23:59:59.000Z

25

Separation of technetium from nuclear waste stream simulants. Final report  

Science Conference Proceedings (OSTI)

The author studied liquid anion exchangers, such as Aliquat-336 nitrate, various pyridinium nitrates, and related salts, so that they may be applied toward a specific process for extracting (partitioning) and recovering {sup 99}TcO{sub 4}{sup {minus}} from nuclear waste streams. Many of the waste streams are caustic and contain a variety of other ions. For this reason, the author studied waste stream simulants that are caustic and contain appropriate concentrations of selected, relevant ions. Methods of measuring the performance of the exchangers and extractant systems included contact experiments. Batch contact experiments were used to determine the forward and reverse extraction parameters as a function of temperature, contact time, phase ratio, concentration, solvent (diluent), and other physical properties. They were also used for stability and competition studies. Specifically, the author investigated the solvent extraction behavior of salts of perrhenate (ReO{sub 4}{sup {minus}}), a stable (non-radioactive) chemical surrogate for {sup 99}TcO{sub 4}{sup {minus}}. Results are discussed for alternate organic solvents; metalloporphyrins, ferrocenes, and N-cetyl pyridium nitrate as alternate extractant salts; electroactive polymers; and recovery of ReO{sub 4}{sup {minus}} and TcO{sub 4}{sup {minus}}.

Strauss, S.H. [Colorado State Univ., Fort Collins, CO (United States). Dept. of Chemistry

1995-09-11T23:59:59.000Z

26

WasteStreamForecast2010.xls  

Office of Environmental Management (EM)

Reporting Reporting Site Disposition Facility Field Stream ID Actual Dispos 2009 Starting Inventory 2010 2010 2011 2012 2013 2014 2015 to 2019 2020 to 2024 2025 to 2029 2030 to 2034 2035 to 2039 2040-50 1 Ames Energy Solutions-Clive (formerly Envirocare) 8020-01 0.00 0.00 0.00 0.00 0.00 20.00 0.00 0.00 20.00 20.00 20.00 0.00 60.00 2 Argonne Area 5 LLW Disposal Unit (NTS) AEL105DOEa 55.12 50.45 72.36 29.22 29.22 29.22 29.22 29.22 0.00 0.00 0.00 0.00 0.00 3 Argonne Area 5 LLW Disposal Unit (NTS) AEL106DOEa 0.38 0.07 0.09 0.21 0.21 0.21 0.21 0.21 0.00 0.00 0.00 0.00 0.00 4 Argonne Area 5 LLW Disposal Unit (NTS) AE-L104DOE 0.19 10.85 11.19 0.42 0.42 0.42 0.42 0.42 0.00 0.00 0.00 0.00 0.00 5 Argonne Area 5 LLW Disposal Unit (NTS) AEL103DOE 74.13 87.37 110.16 30.39 30.39 30.39 30.39 30.39 0.00 0.00 0.00 0.00 0.00 6 Argonne Area 5 LLW Disposal Unit (NTS)

27

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

28

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

29

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

30

Feasibility Study – Using a Solar Evaporator to Reduce the Metalworking Fluid (MWF) Waste Stream  

DOE Green Energy (OSTI)

A solar evaporator was designed, built, and operated to reduce the water-based metalworking fluid waste stream. The evaporator was setup in Waste Management’s barrel lot inside one of the confinement areas. The unit processed three batches of waste fluid during the prototype testing. Initial tests removed 13% of the fluid waste stream. Subsequent modifications to the collector improved the rate to almost 20% per week. Evaluation of the risk during operation showed that even a small spill when associated with precipitation, and the unit placement within a confinement area, gave it the potential to contaminate more fluid that what it could save.

Lazarus, Lloyd

2008-12-03T23:59:59.000Z

31

Hazardous Waste Code Determinations for the First/Second Stage Sludge Waste Stream (IDCs 001, 002, 800)  

Science Conference Proceedings (OSTI)

This document, Hazardous Waste Code Determination for the First/Second-Stage Sludge Waste Stream, summarizes the efforts performed at the Idaho National Engineering and Environmental Laboratory (INEEL) to make a hazardous waste code determination on Item Description Codes (IDCs) 001, 002, and 800 drums. This characterization effort included a thorough review of acceptable knowledge (AK), physical characterization, waste form sampling, chemical analyses, and headspace gas data. This effort included an assessment of pre-Waste Analysis Plan (WAP) solidified sampling and analysis data (referred to as preliminary data). Seventy-five First/Second-Stage Sludge Drums, provided in Table 1-1, have been subjected to core sampling and analysis using the requirements defined in the Quality Assurance Program Plan (QAPP). Based on WAP defined statistical reduction, of preliminary data, a sample size of five was calculated. That is, five additional drums should be core sampled and analyzed. A total of seven drums were sampled, analyzed, and validated in compliance with the WAP criteria. The pre-WAP data (taken under the QAPP) correlated very well with the WAP compliant drum data. As a result, no additional sampling is required. Based upon the information summarized in this document, an accurate hazardous waste determination has been made for the First/Second-Stage Sludge Waste Stream.

Arbon, Rodney Edward

2001-01-01T23:59:59.000Z

32

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

SciTech Connect

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

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

2010-01-30T23:59:59.000Z

33

Method for Sequestering Carbon Dioxide and Sulfur Dioxide Utilizing a Plurality of Waste Streams  

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

Sequestering Carbon Dioxide and Sulfur Dioxide Sequestering Carbon Dioxide and Sulfur Dioxide Utilizing a Plurality of Waste Streams Opportunity The Department of Energy's National Energy Technology Laboratory is seeking licensing partners interested in implementing United States Patent Number 7,922,792 entitled "Method for Sequestering Carbon Dioxide and Sulfur Dioxide Utilizing a Plurality of Waste Streams." Disclosed in this patent is the invention of a neutralization/sequestration method that concomitantly treats bauxite residues from aluminum production processes, as well as brine wastewater from oil and gas production processes. The method uses an integrated approach that coincidentally treats multiple industrial waste by-product streams. The end results include neutralizing caustic

34

An Economic Assessment of Market-Based Approaches to Regulating the Municipal Solid Waste Stream  

E-Print Network (OSTI)

in id. ). The number of mixed waste processing facilitiesWaste separation occurs at mixed waste processing facilitiesban disposal of yard waste in mixed refuse. Variable Rate

Menell, Peter S.

2004-01-01T23:59:59.000Z

35

Department of Energy and Mineral Engineering Spring 2013 Solar Innovations -HVAC and Waste Stream Analysis  

E-Print Network (OSTI)

PENNSTATE Department of Energy and Mineral Engineering Spring 2013 Solar Innovations - HVAC and Waste Stream Analysis Overview There are two problems that were voiced by Solar Innovations, HVAC system design and recycling stream improvement. The HVAC system was not providing even conditioning of office

Demirel, Melik C.

36

Pervaporation process and use in treating waste stream from glycol dehydrator  

DOE Patents (OSTI)

Pervaporation processes and apparatus with few moving parts. Ideally, only one pump is used to provide essentially all of the motive power and driving force needed. The process is particularly useful for handling small streams with flow rates less than about 700 gpd. Specifically, the process can be used to treat waste streams from glycol dehydrator regeneration units.

Kaschemekat, Jurgen (Campbell, CA); Baker, Richard W. (Palo Alto, CA)

1994-01-01T23:59:59.000Z

37

Commercial treatability study capabilities for application to the US Department of Energy`s anticipated mixed waste streams  

SciTech Connect

The U.S. Department of Energy (DOE) has established the Mixed Waste Focus Area (MWFA), which represents a national effort to develop and coordinate treatment solutions for mixed waste among all DOE facilities. The hazardous waste component of mixed waste is regulated under the Resource Conservation and Recovery Act (RCRA), while the radioactive component is regulated under the Atomic Energy Act, as implemented by the DOE, making mixed waste one of the most complex types of waste for the DOE to manage. The MWFA has the mission to support technologies that meet the needs of the DOE`s waste management efforts to characterize, treat, and dispose of mixed waste being generated and stored throughout the DOE complex. The technologies to be supported must meet all regulatory requirements, provide cost and risk improvements over available technologies, and be acceptable to the public. The most notable features of the DOE`s mixed-waste streams are the wide diversity of waste matrices, volumes, radioactivity levels, and RCRA-regulated hazardous contaminants. Table 1-1 is constructed from data from the proposed site treatment plans developed by each DOE site and submitted to DOE Headquarters. The table shows the number of mixed-waste streams and their corresponding volumes. This table illustrates that the DOE has a relatively small number of large-volume mixed-waste streams and a large number of small-volume mixed-waste streams. There are 1,033 mixed-waste streams with volumes less than 1 cubic meter; 1,112 mixed-waste streams with volumes between 1 and 1,000 cubic meters; and only 61 mixed-waste streams with volumes exceeding 1,000 cubic meters.

NONE

1996-07-01T23:59:59.000Z

38

Vitrification of Three Low-Activity Radioactive Waste Streams from Hanford  

Science Conference Proceedings (OSTI)

As part of a demonstration for British Nuclear Fuels Limited, Incorporated (BNFL), the Immobilization Technology Section (ITS) of the Savannah River Technology Center (SRTC) has produced and characterized three low-activity waste (LAW) glasses from Hanford radioactive waste samples. The three LAW glasses were produced from radioactive supernate samples that had been treated by the Waste Processing Technology Section (WPTS) at SRTC to remove most of the radionuclides. These three glasses were produced by mixing the waste streams with between four and nine glass-forming chemicals in platinum/gold crucibles and heating the mixture to between 1120 and 1150 degrees C. Compositions of the resulting glass waste forms were close to the target compositions. Low concentrations of radionuclides in the LAW feed streams and, therefore, in the glass waste forms supported WPTS conclusions that pretreatment had been successful. No crystals were detected in the LAW glasses. In addition, all glass waste forms passed the leach tests that were performed. These included a 20 degrees C Product Consistency Test (PCT) and a modified version of the United States Environmental Protection Agency Toxicity Characteristic Leaching Procedure (TCLP).

Ferrara, D.M.; Crawford, C.L.; Ha, B.C.; Bibler, N.E.

1998-09-01T23:59:59.000Z

39

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...

40

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

DOE Patents (OSTI)

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

Chaiko, D.J.

1993-01-01T23:59:59.000Z

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

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

DOE Patents (OSTI)

A liquid-liquid extraction method for removing metals and hydrous metal colloids from waste streams is provided wherein said waste streams are contacted with a solvent system containing a water-in-oil microemulsion wherein the inverted micelles contain the extracted metal. A silicon alkoxide, either alone or in combination with other metal alkoxide compounds is added to the water-in-oil microemulsion, thereby allowing encapsulation of the extracted metal within a silicon oxide network. Lastly, the now-encapsulated metal is precipitated from the water-in-oil microemulsion phase to yield aggregates of metal-silicate particles having average individual particle sizes of approximately 40 nanometers. 2 figs.

Chaiko, D.J.

1995-03-07T23:59:59.000Z

42

Savannah River Site Waste Isolation Pilot Plant Disposal Program - Acceptable Knowledge Summary Report for Waste Stream: SR-T001-221-HET  

Science Conference Proceedings (OSTI)

This document, along with referenced supporting documents provides a defensible and auditable record of acceptable knowledge for one of the waste streams from the FB-Line. This heterogeneous debris transuranic waste stream was generated after January 25, 1990 and before March 20, 1997. The waste was packaged in 55-gallon drums, then shipped to the transuranic waste storage facility in ''E'' area of the Savannah River Site. This acceptable knowledge report includes information relating to the facility's history, configuration, equipment, process operations and waste management practices. Information contained in this report was obtained from numerous sources including: facility safety basis documentation, historical document archives, generator and storage facility waste records and documents, and interviews with cognizant personnel.

Lunsford, G.F.

2001-01-24T23:59:59.000Z

43

An Economic Assessment of Market-Based Approaches to Regulating the Municipal Solid Waste Stream  

E-Print Network (OSTI)

generation of biofuel waste energy and increases the rate ofthe design and siting of waste to energy incinerators. Theregion is burned in waste-to-energy incineration facilities.

Menell, Peter S.

2004-01-01T23:59:59.000Z

44

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

45

ASSESSMENT OF RADIOACTIVE AND NON-RADIOACTIVE CONTAMINANTS FOUND IN LOW LEVEL RADIOACTIVE WASTE STREAMS  

Science Conference Proceedings (OSTI)

This paper describes and presents the findings from two studies undertaken for the European Commission to assess the long-term impact upon the environment and human health of non-radioactive contaminants found in various low level radioactive waste streams. The initial study investigated the application of safety assessment approaches developed for radioactive contaminants to the assessment of nonradioactive contaminants in low level radioactive waste. It demonstrated how disposal limits could be derived for a range of non-radioactive contaminants and generic disposal facilities. The follow-up study used the same approach but undertook more detailed, disposal system specific calculations, assessing the impacts of both the non-radioactive and radioactive contaminants. The calculations undertaken indicated that it is prudent to consider non-radioactive, as well as radioactive contaminants, when assessing the impacts of low level radioactive waste disposal. For some waste streams with relatively low concentrations of radionuclides, the potential post-closure disposal impacts from non-radioactive contaminants can be comparable with the potential radiological impacts. For such waste streams there is therefore an added incentive to explore options for recycling the materials involved wherever possible.

R.H. Little, P.R. Maul, J.S.S. Penfoldag

2003-02-27T23:59:59.000Z

46

Independent review of inappropriate identification, storage and treatment methods of polychlorinated biphenyl waste streams  

SciTech Connect

The purpose of the review was to evaluate incidents involving the inappropriate identification, storage, and treatment methods associated with polychlorinated biphenyl (PCB) waste streams originating from the V-tank system at the Test Area North (TAN). The team was instructed to perform a comprehensive review of Lockheed Martin Idaho Technologies Company (LMITCO`s) compliance programs related to these incidents to assess the adequacy and effectiveness of the management program in all respects including: adequacy of the waste management program in meeting all LMITCO requirements and regulations; adequacy of policies, plans, and procedures in addressing and implementing all federal and state requirements and regulations; and compliance status of LMITCO, LMITCO contract team members, and LMITCO contract/team member subcontractor personnel with established PCB management policies, plans, and procedures. The V-Tanks are part of an intermediate waste disposal system and are located at the Technical Support Facility (TSF) at TAN at the Idaho National Engineering and Environmental Laboratory (INEEL). The IRT evaluated how a waste was characterized, managed, and information was documented; however, they did not take control of wastes or ensure followup was performed on all waste streams that may have been generated from the V-Tanks. The team has also subsequently learned that the Environmental Restoration (ER) program is revising the plans for the decontamination and decommissioning of the intermediate waste disposal system based on new information listed and PCB wastes. The team has not reviewed those in-process changes. The source of PCB in the V-Tank is suspected to be a spill of hydraulic fluid in 1968.

1997-07-01T23:59:59.000Z

47

New Innovations in Highly Ion Specific Media for Recalcitrant Waste stream Radioisotopes  

SciTech Connect

Specialty ion specific media were examined and developed for, not only pre- and post-outage waste streams, but also for very difficult outage waste streams. This work was carried out on first surrogate waste streams, then laboratory samples of actual waste streams, and, finally, actual on-site waste streams. This study was particularly focused on PWR wastewaters such as Floor Drain Tank (FDT), Boron Waste Storage Tank (BWST), and Waste Treatment Tank (WTT, or discharge tank). Over the last half decade, or so, treatment technologies have so greatly improved and discharge levels have become so low, that certain particularly problematic isotopes, recalcitrant to current treatment skids, are all that remain prior to discharge. In reality, they have always been present, but overshadowed by the more prevalent and higher activity isotopes. Such recalcitrants include cobalt, especially Co 58 [both ionic/soluble (total dissolved solids, TDS) and colloidal (total suspended solids, TSS)] and antimony (Sb). The former is present in most FDT and BWST wastewaters, while the Sb is primarily present in BWST waste streams. The reasons Co 58 can be elusive to granulated activated carbon (GAC), ultrafiltration (UF) and ion exchange (IX) demineralizers is that it forms submicron colloids as well as has a tendency to form metal complexes with chelating agents (e.g., ethylene diamine tetraacetic acid, or EDTA). Such colloids and non-charged complexes will pass through the entire treatment skid. Antimony (Sb) on the other hand, has little or no ionic charge, and will, likewise, pass through both the filtration and de-min skids into the discharge tanks. While the latter will sometimes (the anionic vs. the cationic or neutral species) be removed on the anion bed(s), it will slough off (snow-plow effect) when a higher affinity anion (iodine slugs, etc.) comes along; thus causing effluents not meeting discharge criteria. The answer to these problems found in this study, during an actual Nuclear Power Plant (NPP) outage cycle and recovery (four months), was the down-select and development of a number of highly ion specific media for the specific removal of such elusive isotopes. Over three dozen media including standard cation and anion ion exchangers, specialty IX, standard carbons, and, finally, chemically doped media (e.g., carbon and alumina substrates). The latter involved doping with iron, manganese, and even metals. The media down-select was carried out on actual plant waste streams so that all possible outage affects were accounted for, and distribution coefficients (Kd's) were determined (vs. decontamination factors, DF's, or percent removals). Such Kd's, in milliliters of solution per gram of media (mug), produce data indicative of the longevity of the media in that particular waste stream. Herein, the down-select is reported in Pareto (decreasing order) tables. Further affects such as the presence of high cobalt concentrations, high boron concentrations, the presence of hydrazine and chelating agents, and extreme pH conditions. Of particular importance here is to avoid the affinity of competing ions (e.g., a Sb specific media having more than a slight affinity for Co). The latter results in the snow-plow effect of sloughing off 3 to 4 times the cobalt into the effluent as was in the feed upon picking up the Sb. The study was quite successful and resulted in the development of and selection of a resin-type and two granular media for antimony removal, and two resin-types and a granular media for cobalt removal. The decontamination factors for both media were hundreds to thousands of times that of the full filtration and de-min. (authors)

Denton, M. S.; Wilson, J.; Ahrendt, M. [RWE NUKEM Corporation (RNC), 800 Oak Ridge Tnpk., Suite A701, Oak Ridge, TN 37830 (United States); Bostick, W. D. [Materials and Chemistry Laboratory (MCL), Inc., East Tennessee Technology Park, Building K-1006, 2010 Highway 58, Suite 1000, Oak Ridge, TN 37830 (United States); DeSilva, F.; Meyers, P. [ResinTech, Inc., 1 ResinTech Plaza, 160 Cooper Road, West Berlin, NJ 08091 (United States)

2006-07-01T23:59:59.000Z

48

Grout formulation for disposal of low-level and hazardous waste streams containing fluoride  

DOE Patents (OSTI)

A composition and related process for disposal of hazardous waste streams containing fluoride in cement-based materials is disclosed. the presence of fluoride in cement-based materials is disclosed. The presence of fluoride in waste materials acts as a set retarder and as a result, prevents cement-based grouts from setting. This problem is overcome by the present invention wherein calcium hydroxide is incorporated into the dry-solid portion of the grout mix. The calcium hydroxide renders the fluoride insoluble, allowing the grout to set up and immobilize all hazardous constituents of concern. 4 tabs.

McDaniel, E.W.; Sams, T.L.; Tallent, O.K.

1987-06-02T23:59:59.000Z

49

USE OF STREAM ANALYZER FOR SOLUBILITY PREDICTIONS OF SELECTED HANFORD TANK WASTE  

SciTech Connect

The Hanford Tank Waste Operations Simulator (HTWOS) models the mission to manage, retrieve, treat and vitrify Hanford waste for long-term storage and disposal. HTWOS is a dynamic, flowsheet, mass balance model of waste retrieval and treatment activities. It is used to evaluate the impact of changes on long-term mission planning. The project is to create and evaluate the integrated solubility model (ISM). The ISM is a first step in improving the chemistry basis in HTWOS. On principal the ISM is better than the current HTWOS solubility. ISM solids predictions match the experimental data well, with a few exceptions. ISM predictions are consistent with Stream Analyzer predictions except for chromium. HTWOS is producing more realistic results with the ISM.

PIERSON KL; BELSHER JD; HO QT

2012-11-02T23:59:59.000Z

50

Removal of pertechnetate from simulated nuclear waste streams using supported zerovalent iron  

SciTech Connect

The application of nanoparticles of predominantly zerovalent iron (nanoiron), either unsupported or supported, to the separation and reduction of pertechnetate anions (TcO4-) from complex waste mixtures was investigated as an alternative approach to current waste-processing schemes. Although applicable to pertechnetate-containing waste streams in general, the research discussed here was directed at two specific potential applications at the U.S. Department of Energy's Hanford Site: (1) the direct removal of pertechnetate from highly alkaline solutions, typical of those found in Hanford tank waste, and (2) the removal of dilute pertechnetate from near-neutral solutions, typical of the eluate streams from commercial organic ion-exchange resins that may be used to remediate Hanford tank wastes. It was envisioned that both applications would involve the subsequent encapsulation of the loaded sorbent material into a separate waste form. A high surface area (>200 M2/g) base-stable, nanocrystalline zirconia was used as a support for nanoiron for tests with highly alkaline solutions, while a silica gel support was used for tests with near-neutral solutions. It was shown that after 24 h of contact time, the high surface area zirconia supported nanoiron sorbent removed about 50percent (K-d = 370 L/kg) of the pertechnetate from a pH 14 tank waste simulant containing 0.51 mM TCO4- and large concentrations of Na+, OH-, NO3-, and CO32- for a phase ratio of 360 L simulant per kg of sorbent. It was also shown that after 18 h of contact time, the silica-supported nanoiron removed>95percent pertechnetate from a neutral pH eluate simulant containing 0.076 mM TcO4_ for a phase ratio of 290 L/kg. It was determined that in all cases, nanoiron reduced the Tc(VII) to Tc(IV), or possibly to Tc(V), through a redox reaction. Finally, it was demonstrated that a mixture of 20 mass percent of the solid reaction products obtained from contacting zirconia- supported nanoiron with an alkaline waste solution containing Re(VII), a surrogate for Tc(VII), with 80 mass percent alkali borosilicate based frit heat-treated at 700 degrees C for 4 h sintered into an easily handled glass composite waste form.

Darab, John; Amonette, Alexandra; Burke, Deborah; Orr, Robert; Ponder, Sherman; Schrick, Bettina; Mallouk, Thomas; Lukens, Wayne; Caulder, Dana; Shuh, David

2007-07-11T23:59:59.000Z

51

Recycle Plastic Waste Recommended Action  

E-Print Network (OSTI)

AR No. 5 Recycle Plastic Waste Recommended Action Separate scrap plastic bag waste from solid waste stream and recycle. This can be accomplished by either arranging for no-cost pick-up of loose waste or by selling baled waste material. Assessment Recommendation Summary Recommended Waste Cost Implementation

Tullos, Desiree

52

Characterization and monitoring of 300 Area Facility liquid waste streams: Status report  

SciTech Connect

This report summarizes the results of characterizing and monitoring the following sources during a portion of this year: liquid waste streams from Buildings 331, 320, and 3720; treated and untreated Columbia River water; and water at the confluence of the waste streams (that is, end-of-pipe). Characterization and monitoring data were evaluated for samples collected between March 22 and June 21, 1994, and subsequently analyzed for hazardous chemicals, radioactivity, and general parameters. Except for bis(2-ethylhexyl)phthalate, concentrations of chemicals detected and parameters measured at end-of-pipe were below the US Environmental Protection Agency existing and proposed drinking water standards. The source of the chemicals, except bis(2-ethylhexyl)phthalate, is not currently known. The bis(2-ethylhexyl)phthalate is probably an artifact of the plastic tubing used in the early stages of the sampling program. This practice was stopped. Concentrations and clearance times for contaminants at end-of-pipe depended strongly on source concentration at the facility release point, waste stream flow rates, dispersion, and the mechanical action of sumps. When present, the action of sumps had the greatest impact on contaminant clearance times. In the absence of sump activity, dispersion and flow rate were the controlling factors.

Manke, K.L. [ed.; Riley, R.G.; Ballinger, M.Y.; Damberg, E.G.; Evans, J.C.; Ikenberry, A.S.; Olsen, K.B.; Ozanich, R.M.; Thompson, C.J.

1994-09-01T23:59:59.000Z

53

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

SciTech Connect

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

1993-04-01T23:59:59.000Z

54

DM100 AND DM1200 MELTER TESTING WITH HIGH WASTE LOADING GLASS FORMULATIONS FOR HANFORD HIGH-ALUMINUM HLW STREAMS  

SciTech Connect

This Test Plan describes work to support the development and testing of high waste loading glass formulations that achieve high glass melting rates for Hanford high aluminum high level waste (HLW). In particular, the present testing is designed to evaluate the effect of using low activity waste (LAW) waste streams as a source of sodium in place ofchemical additives, sugar or cellulose as a reductant, boehmite as an aluminum source, and further enhancements to waste processing rate while meeting all processing and product quality requirements. The work will include preparation and characterization of crucible melts in support of subsequent DuraMelter 100 (DM 100) tests designed to examine the effects of enhanced glass formulations, glass processing temperature, incorporation of the LAW waste stream as a sodium source, type of organic reductant, and feed solids content on waste processing rate and product quality. Also included is a confirmatory test on the HLW Pilot Melter (DM1200) with a composition selected from those tested on the DM100. This work builds on previous work performed at the Vitreous State Laboratory (VSL) for Department of Energy's (DOE's) Office of River Protection (ORP) to increase waste loading and processing rates for high-iron HLW waste streams as well as previous tests conducted for ORP on the same waste composition. This Test Plan is prepared in response to an ORP-supplied statement of work. It is currently estimated that the number of HLW canisters to be produced in the Hanford Tank Waste Treatment and Immobilization Plant (WTP) is about 12,500. This estimate is based upon the inventory ofthe tank wastes, the anticipated performance of the sludge treatment processes, and current understanding of the capability of the borosilicate glass waste form. The WTP HLW melter design, unlike earlier DOE melter designs, incorporates an active glass bubbler system. The bubblers create active glass pool convection and thereby improve heat transfer and glass melting rate. The WTP HLW melter has a glass surface area of 3.75 m{sup 2} and depth of {approx}1.1 m. The two melters in the HLW facility together are designed to produce up to 7.5 MT of glass per day at 100% availability. Further increases in HLW waste processing rates can potentially be achieved by increasing the melter operating temperature above 1150 C and by increasing the waste loading in the glass product Increasing the waste loading also has the added benefit of decreasing the number of canisters for storage. The current estimates and glass formulation efforts have been conservative in terms of achievable waste loadings. These formulations have been specified to ensure that the glasses are homogenous, contain essentially no crystalline phases, are processable in joule-heated, ceramic-lined melters and meet WTP contract requirements. The WTP's overall mission will require the immobilization oftank waste compositions that are dominated by mixtures of aluminum (Al), chromium (Cr), bismuth (Bi), iron (Fe), phosphorous (P), zirconium (Zr), and sulfur (S) compounds as waste-limiting components. Glass compositions for these waste mixtures have been developed based upon previous experience and current glass property models. Recently, DOE has initiated a testing program to develop and characterize HLW glasses with higher waste loadings. Results of this work have demonstrated the feasibility of increases in waste-loading from about 25 wt% to 33-50 wt% (based on oxide loading) in the glass depending on the waste stream. It is expected that these higher waste loading glasses will reduce the HLW canister production requirement by about 25% or more.

KRUGER AA; MATLACK KS; KOT WK; PEGG IL; JOSEPH I

2009-12-30T23:59:59.000Z

55

Acceptable Knowledge Summary Report for Waste Stream: SR-T001-221F-HET/Drums  

Science Conference Proceedings (OSTI)

Since beginning operations in 1954, the Department of Energy's Savannah River Site FB-Line conducted atomic energy defense activities consistent with the listing in Section 10101(3) of the Nuclear Waste Policy Act of 1982. The facility mission was to process and convert dilute plutonium solution into highly purified weapons grade plutonium metal. As a result of various activities conducted in support of the mission (e.g., operation, maintenance, repair, clean up, and facility modifications), the facility generated transuranic waste. This document, along with referenced supporting documents, provides a defensible and auditable record of acceptable knowledge for one of the waste streams from the FB-Line. The waste was packaged in 55-gallon drums, then shipped to the transuranic waste storage facility in ''E'' area of the Savannah River Site. This acceptable knowledge report includes information relating to the facility's history, configuration,equipment, process operations, and waste management practices.

Lunsford, G.F.

1999-08-23T23:59:59.000Z

56

WIPP Waste Information System Waste Container Data Report  

E-Print Network (OSTI)

WIPP Waste Information System Waste Container Data Report 06/06/2008 07:50 2.6 % LASB00411 % % Report Date Run by Report Site Id Container Number Waste Stream Data Status Code PEARCYM Version RP0360 Selection Criteria - Total Pages PRD02Instance 5 #12;Waste Isolation Pilot Plant Waste Container Data Report

57

WIPP Waste Information System Waste Container Data Report  

E-Print Network (OSTI)

WIPP Waste Information System Waste Container Data Report 06/06/2008 07:49 2.6 % LAS817174 % % Report Date Run by Report Site Id Container Number Waste Stream Data Status Code PEARCYM Version RP0360 Selection Criteria - Total Pages PRD02Instance 5 #12;Waste Isolation Pilot Plant Waste Container Data Report

58

Characterization and monitoring of 300 Area facility liquid waste streams: 1994 Annual report  

Science Conference Proceedings (OSTI)

This report summarizes the results of characterizing and monitoring the following sources during calendar year 1994: liquid waste streams from Buildings 306, 320, 324, 326, 331, and 3720 in the 300 Area of Hanford Site and managed by the Pacific Northwest Laboratory; treated and untreated Columbia River water (influent); and water at the confluence of the waste streams (that is, end-of-pipe). Data were collected from March to December before the sampling system installation was completed. Data from this initial part of the program are considered tentative. Samples collected were analyzed for chemicals, radioactivity, and general parameters. In general, the concentrations of chemical and radiological constituents and parameters in building wastewaters which were sampled and analyzed during CY 1994 were similar to historical data. Exceptions were the occasional observances of high concentrations of chloride, nitrate, and sodium that are believed to be associated with excursions that were occurring when the samples were collected. Occasional observances of high concentrations of a few solvents also appeared to be associated with infrequent building r eases. During calendar year 1994, nitrate, aluminum, copper, lead, zinc, bis(2-ethylhexyl) phthalate, and gross beta exceeded US Environmental Protection Agency maximum contaminant levels.

Riley, R.G.; Ballinger, M.Y.; Damberg, E.G.; Evans, J.C.; Julya, J.L.; Olsen, K.B.; Ozanich, R.M.; Thompson, C.J.; Vogel, H.R.

1995-04-01T23:59:59.000Z

59

Case study and presentation of the DOE treatability group concept for low-level and mixed waste streams  

SciTech Connect

The Federal Facility Compliance Act of 1992 requires the US Department of Energy (DOE) to prepare an inventory report of its mixed waste and treatment capacities and technologies. Grouping waste streams according to technological requirements is the logical means of matching waste streams to treatment technologies, and streamlines the effort of identifying technology development needs. To provide consistency, DOE has developed a standard methodology for categorizing waste into treatability groups based on three characteristic parameters: radiological, bulk physical/chemical form, and regulated contaminant. Based on category and component definitions in the methodology, descriptive codes or strings of codes are assigned under each parameter, resulting in a waste characterization amenable to a computerized format for query and sort functions. By using only the applicable parameters, this methodology can be applied to all waste types generated within the DOE complex: radioactive, hazardous, mixed, and sanitary/municipal. Implementation of this methodology will assist the individual sites and DOE Headquarters in analyzing waste management technology and facility needs.

Kirkpatrick, T.D. [Lockheed Idaho Technologies, Germantown, MD (United States); Heath, B.A. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); Davis, K.D. [Roy F. Weston, Inc., Idaho Falls, ID (United States)

1994-12-31T23:59:59.000Z

60

ZERO WASTE.  

E-Print Network (OSTI)

??The aim of the thesis was to develop a clear vision on better waste management system. The thesis introduced the sustainable waste management along with… (more)

Upadhyaya, Luv

2013-01-01T23:59:59.000Z

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

Tellurite glass as a waste form for a simulated mixed chloride waste stream: Candidate materials selection and initial testing  

Science Conference Proceedings (OSTI)

Tellurite glasses have been researched widely for the last 60 years since they were first introduced by Stanworth. These glasses have been primarily used in research applications as glass host materials for lasers and as non-linear optical materials, though many other uses exist in the literature. Tellurite glasses have long since been used as hosts for various, and even sometimes mixed, halogens (i.e., multiple chlorides or even chlorides and iodides). Thus, it was reasonable to expect that these types of glasses could be used as a waste form to immobilize a combination of mixed chlorides present in the electrochemical separations process involved with fuel separations and processing from nuclear reactors. Many of the properties related to waste forms (e.g., chemical durability, maximum chloride loading) for these materials are unknown and thus, in this study, several different types of tellurite glasses were made and their properties studied to determine if such a candidate waste form could be fabricated with these glasses. One of the formulations studied was a lead tellurite glass, which had a low sodium release and is on-par with high-level waste silicate glass waste forms.

Riley, Brian J.; Rieck, Bennett T.; McCloy, John S.; Crum, Jarrod V.; Sundaram, S. K.; Vienna, John D.

2012-02-02T23:59:59.000Z

62

Mixed Waste Characterization Guidelines  

Science Conference Proceedings (OSTI)

This report presents an overview of the process of characterizing potential mixed waste streams from nuclear power plants. Utility experts developed these guidelines to help guide utility personnel through the characterization process and provide a mechanism for properly documenting the characterization of individual waste streams.

1995-12-31T23:59:59.000Z

63

Nuclear waste solutions  

DOE Patents (OSTI)

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

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

1987-01-01T23:59:59.000Z

64

Characterization of past and present solid waste streams from 231-Z  

SciTech Connect

During the next two decades the transuranic (TRU) wastes now stored in the burial trenches and storage facilities at the Hanford Site are to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant near Carlsbad, New Mexico for final disposal. Over 8% of the TRU waste to be retrieved for shipment to the Waste Isolation Pilot Plant has been generated at the Plutonium Metallurgy Laboratory (231-Z) Facility. The purpose of this report is to characterize the radioactive solid wastes generated by 231-Z using process knowledge, existing records and oral history interviews. Since 1944 research and development programs utilizing plutonium have been conducted at 231-Z in the fields of physical metallurgy, property determination, alloy development, and process development. The following are sources of solid waste generation at the 231-Z Facility: (1) General Weapons Development Program, (2) process waste from gloveboxes, (3) numerous classified research and development programs, (4) advanced decontamination and decommissioning technologies, including sectioning, vibratory finishing, electropolishing, solution process, and small bench-scale work, (5) general laboratory procedures, (6) foundry area, (7) housekeeping activities, and (8) four cleanout campaigns. All solid wastes originating at 231-Z were packaged for onsite-offsite storage or disposal. Waste packaging and reporting requirements have undergone significant changes throughout the history of 231-Z. Current and historical procedures are provided in Section 4.0. Information on the radioactive wastes generated at 231-Z can be found in a number of documents and databases, most importantly the Solid Waste Information and Tracking System database and Solid Waste Burial Records. Facility personnel also provide excellent information about past waste generation and the procedures used to handle that waste. Section 5.0 was compiled using these sources.

Pottmeyer, J.A.; DeLorenzo, D.S.; Weyns-Rollosson, M.I.; Berkwitz, D.E.; Vejvoda, E.J. [Los Alamos Technical Associates, Inc., NM (US); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (US)

1993-06-01T23:59:59.000Z

65

Commercial treatability study capabilities for application to the US Department of Energy`s anticipated mixed waste streams. Revision 1  

SciTech Connect

US DOE mixed low-level and mixed transuranic waste inventory was estimated at 181,000 cubic meters (about 2,000 waste streams). Treatability studies may be used as part of DOE`s mixed waste management program. Commercial treatability study suppliers have been identified that either have current capability in their own facilities or have access to licensed facilities. Numerous federal and state regulations, as well as DOE Order 5820.2A, impact the performance of treatability studies. Generators, transporters, and treatability study facilities are subject to regulation. From a mixed- waste standpoint, a key requirement is that the treatability study facility must have an NRC or state license that allows it to possess radioactive materials. From a RCRA perspective, the facility must support treatability study activities with the applicable plans, reports, and documentation. If PCBs are present in the waste, TSCA will also be an issue. CERCLA requirements may apply, and both DOE and NRC regulations will impact the transportation of DOE mixed waste to an off-site treatment facility. DOE waste managers will need to be cognizant of all applicable regulations as mixed-waste treatability study programs are initiated.

1996-09-01T23:59:59.000Z

66

Three dimensional electrode for the electrolytic removal of contaminants from aqueous waste streams  

DOE Patents (OSTI)

Efficient and cost-effective electrochemical devices and processes for the remediation of aqueous waste streams. The invention provides electrolytic cells having a high surface area spouted electrode for removal of heavy metals and oxidation of organics from aqueous environments. Heavy metal ions are reduced, deposited on cathode particles of a spouted bed cathode and removed from solution. Organics are efficiently oxidized at anode particles of a spouted bed anode and removed from solution. The method of this inventions employs an electrochemical cell having an anolyte compartment and a catholyte compartment, separated by a microporous membrane, in and through which compartments anolyte and catholyte, respectively, are circulated. A spouted-bed electrode is employed as the cathode for metal deposition from contaminated aqueous media introduced as catholyte and as the anode for oxidation of organics from contaminated aqueous media introduced as anolyte.

Spiegel, Ella F. (Louisville, CO); Sammells, Anthony F. (Boulder, CO)

2001-01-01T23:59:59.000Z

67

Estimating Waste Inventory and Waste Tank Characterization |...  

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

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

68

Waste Management & Research172 Waste Manage Res 2003: 21: 172177  

E-Print Network (OSTI)

Waste Management & Research172 Waste Manage Res 2003: 21: 172­177 Printed in UK ­ all rights reserved Copyright © ISWA 2003 Waste Management & Research ISSN 0734­242X In many market segments of PVC in Germany increased by 9%, the fastest growth rate of all plastics. The waste stream in Germany

Columbia University

69

SOLIDIFICATION OF THE HANFORD LAW WASTE STREAM PRODUCED AS A RESULT OF NEAR-TANK CONTINUOUS SLUDGE LEACHING AND SODIUM HYDROXIDE RECOVERY  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE), Office of River Protection (ORP), is responsible for the remediation and stabilization of the Hanford Site tank farms, including 53 million gallons of highly radioactive mixed wasted waste contained in 177 underground tanks. The plan calls for all waste retrieved from the tanks to be transferred to the Waste Treatment Plant (WTP). The WTP will consist of three primary facilities including pretreatment facilities for Low Activity Waste (LAW) to remove aluminum, chromium and other solids and radioisotopes that are undesirable in the High Level Waste (HLW) stream. Removal of aluminum from HLW sludge can be accomplished through continuous sludge leaching of the aluminum from the HLW sludge as sodium aluminate; however, this process will introduce a significant amount of sodium hydroxide into the waste stream and consequently will increase the volume of waste to be dispositioned. A sodium recovery process is needed to remove the sodium hydroxide and recycle it back to the aluminum dissolution process. The resulting LAW waste stream has a high concentration of aluminum and sodium and will require alternative immobilization methods. Five waste forms were evaluated for immobilization of LAW at Hanford after the sodium recovery process. The waste forms considered for these two waste streams include low temperature processes (Saltstone/Cast stone and geopolymers), intermediate temperature processes (steam reforming and phosphate glasses) and high temperature processes (vitrification). These immobilization methods and the waste forms produced were evaluated for (1) compliance with the Performance Assessment (PA) requirements for disposal at the IDF, (2) waste form volume (waste loading), and (3) compatibility with the tank farms and systems. The iron phosphate glasses tested using the product consistency test had normalized release rates lower than the waste form requirements although the CCC glasses had higher release rates than the quenched glasses. However, the waste form failed to meet the vapor hydration test criteria listed in the WTP contract. In addition, the waste loading in the phosphate glasses were not as high as other candidate waste forms. Vitrification of HLW waste as borosilicate glass is a proven process; however the HLW and LAW streams at Hanford can vary significantly from waste currently being immobilized. The ccc glasses show lower release rates for B and Na than the quenched glasses and all glasses meet the acceptance criterion of < 4 g/L. Glass samples spiked with Re{sub 2}O{sub 7} also passed the PCT test. However, further vapor hydration testing must be performed since all the samples cracked and the test could not be performed. The waste loading of the iron phosphate and borosilicate glasses are approximately 20 and 25% respectively. The steam reforming process produced the predicted waste form for both the high and low aluminate waste streams. The predicted waste loadings for the monolithic samples is approximately 39%, which is higher than the glass waste forms; however, at the time of this report, no monolithic samples were made and therefore compliance with the PA cannot be determined. The waste loading in the geopolymer is approximately 40% but can vary with the sodium hydroxide content in the waste stream. Initial geopolymer mixes revealed compressive strengths that are greater than 500 psi for the low aluminate mixes and less than 500 psi for the high aluminate mixes. Further work testing needs to be performed to formulate a geopolymer waste form made using a high aluminate salt solution. A cementitious waste form has the advantage that the process is performed at ambient conditions and is a proven process currently in use for LAW disposal. The Saltstone/Cast Stone formulated using low and high aluminate salt solutions retained at least 97% of the Re that was added to the mix as a dopant. While this data is promising, additional leaching testing must be performed to show compliance with the PA. Compressive strength tests must also be performed on the Cast Ston

Reigel, M.; Johnson, F.; Crawford, C.; Jantzen, C.

2011-09-20T23:59:59.000Z

70

Evaluation of the Capabilities of the Hanford Reservation and Envirocare of Utah for Disposal of Potentially Problematic Mixed Low-Level Waste Streams  

E-Print Network (OSTI)

The U.S. Department of Energy's (DOE) Mixed Waste Focus Area is developing a program to address and resolve issues associated with final waste form performance in treating and disposing of DOE's mixed lowlevel waste (MLLW) inventory. A key issue for the program is identifying MLLW streams that may be problematic for disposal. Previous reports have quantified and qualified the capabilities of fifteen DOE sites for MLLW disposal and provided volume and radionuclide concentration estimates for treated MLLW based on the DOE inventory. Scoping-level analyses indicated that 101 waste streams identified in this report (approximately 6250 m 3 of the estimated total treated MLLW) had radionuclide concentrations that may make their disposal problematic. The radionuclide concentrations of these waste streams were compared with the waste acceptance criteria (WAC) for a DOE disposal facility at Hanford and for Envirocare's commercial disposal facility for MLLW in Utah. Of the treated MLLW volume ...

Prepared For The; Robert D. Waters; Phillip I. Pohl; Wu-ching Cheng; Marilyn M. Gruebel; Timothy A. Wheeler; Brenda S. Langkopf

1998-01-01T23:59:59.000Z

71

Urban Wood Waste Resource Assessment  

DOE Green Energy (OSTI)

This study collected and analyzed data on urban wood waste resources in 30 randomly selected metropolitan areas in the United States. Three major categories wood wastes disposed with, or recovered from, the municipal solid waste stream; industrial wood wastes such as wood scraps and sawdust from pallet recycling, woodworking shops, and lumberyards; and wood in construction/demolition and land clearing debris.

Wiltsee, G.

1998-11-20T23:59:59.000Z

72

Hanford Waste Vitrification Plant  

SciTech Connect

The Hanford Waste Vitrification Plant (HWVP) is being designed to immobilize pretreated Hanford high-level waste and transuranic waste in borosilicate glass contained in stainless steel canisters. Testing is being conducted in the HWVP Technology Development Project to ensure that adapted technologies are applicable to the candidate Hanford wastes and to generate information for waste form qualification. Empirical modeling is being conducted to define a glass composition range consistent with process and waste form qualification requirements. Laboratory studies are conducted to determine process stream properties, characterize the redox chemistry of the melter feed as a basis for controlling melt foaming and evaluate zeolite sorption materials for process waste treatment. Pilot-scale tests have been performed with simulated melter feed to access filtration for solids removal from process wastes, evaluate vitrification process performance and assess offgas equipment performance. Process equipment construction materials are being selected based on literature review, corrosion testing, and performance in pilot-scale testing. 3 figs., 6 tabs.

Larson, D.E.; Allen, C.R. (Pacific Northwest Lab., Richland, WA (United States)); Kruger, O.L.; Weber, E.T. (Westinghouse Hanford Co., Richland, WA (United States))

1991-10-01T23:59:59.000Z

73

Materials Science of Nuclear Waste Management I  

Science Conference Proceedings (OSTI)

Mar 6, 2013 ... Separation of the nuclear waste stream into actinides and fission products offers new opportunities for development of ceramic waste forms.

74

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

75

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

76

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

77

Hazardous Waste  

Science Conference Proceedings (OSTI)

Table 6   General refractory disposal options...D landfill (b) Characterized hazardous waste by TCLP

78

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

E-Print Network (OSTI)

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

Russell, Lynn

79

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

E-Print Network (OSTI)

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

Firtel, Richard A.

80

DOE Waste Treatability Group Guidance  

Science Conference Proceedings (OSTI)

This guidance presents a method and definitions for aggregating U.S. Department of Energy (DOE) waste into streams and treatability groups based on characteristic parameters that influence waste management technology needs. Adaptable to all DOE waste types (i.e., radioactive waste, hazardous waste, mixed waste, sanitary waste), the guidance establishes categories and definitions that reflect variations within the radiological, matrix (e.g., bulk physical/chemical form), and regulated contaminant characteristics of DOE waste. Beginning at the waste container level, the guidance presents a logical approach to implementing the characteristic parameter categories as part of the basis for defining waste streams and as the sole basis for assigning streams to treatability groups. Implementation of this guidance at each DOE site will facilitate the development of technically defined, site-specific waste stream data sets to support waste management planning and reporting activities. Consistent implementation at all of the sites will enable aggregation of the site-specific waste stream data sets into comparable national data sets to support these activities at a DOE complex-wide level.

Kirkpatrick, T.D.

1995-01-01T23:59:59.000Z

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

Reducing the solid waste stream: reuse and recycling at Lawrence Livermore National Laboratory  

Science Conference Proceedings (OSTI)

In Fiscal Year (FY) 1996 Lawrence Livermore National Laboratory (LLNL) increased its solid waste diversion by 365 percent over FY 1992 in five solid waste categories - paper, cardboard, wood, metals, and miscellaneous. (LLNL`s fiscal year is from October 1 to September 30.) LLNL reused/ recycled 6,387 tons of waste, including 340 tons of paper, 455 tons of scrap wood, 1,509 tons of metals, and 3,830 tons of asphalt and concrete (Table1). An additional 63 tons was diverted from landfills by donating excess food, selling toner cartridges for reconditioning, using rechargeable batteries, redirecting surplus equipment to other government agencies and schools, and comporting plant clippings. LLNL also successfully expanded its demonstration program to recycle and reuse construction and demolition debris as part of its facility-wide, comprehensive solid waste reduction programs.

Wilson, K. L.

1997-08-01T23:59:59.000Z

82

Removal of pertechnetate from simulated nuclear waste streams using supported zerovalent iron  

E-Print Network (OSTI)

3. ?? TM/JD 2. Westinghouse Hanford Co. , Report WHC-SD-WM-Department of Energy’s Hanford Site: (1) the direct removaltypical of those found in Hanford tank waste; and (2) the

Darab, John

2008-01-01T23:59:59.000Z

83

Acceptable Knowledge Summary Report for Mixed TRU Waste Streams: SR-W026-221F-HET-A through D  

Science Conference Proceedings (OSTI)

This document, along with referenced supporting documents provides a defensible and auditable record of acceptable knowledge for the heterogeneous debris mixed transuranic waste streams generated in the FB-Line after January 25, 1990 and before March 20, 1997.

Lunsford, G.F.

2001-10-02T23:59:59.000Z

84

Characterization of past and present solid waste streams from the Plutonium-Uranium Extraction Plant  

Science Conference Proceedings (OSTI)

During the next two decades the transuranic wastes, now stored in the burial trenches and storage facilities at the Hanford Site, are to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant near Carlsbad, New Mexico for final disposal. Over 7% of the transuranic waste to be retrieved for shipment to the Waste Isolation Pilot Plant has been generated at the Plutonium-Uranium Extraction (PUREX) Plant. The purpose of this report is to characterize the radioactive solid wastes generated by PUREX using process knowledge, existing records, and oral history interviews. The PUREX Plant is currently operated by the Westinghouse Hanford Company for the US Department of Energy and is now in standby status while being prepared for permanent shutdown. The PUREX Plant is a collection of facilities that has been used primarily to separate plutonium for nuclear weapons from spent fuel that had been irradiated in the Hanford Site`s defense reactors. Originally designed to reprocess aluminum-clad uranium fuel, the plant was modified to reprocess zirconium alloy clad fuel elements from the Hanford Site`s N Reactor. PUREX has provided plutonium for research reactor development, safety programs, and defense. In addition, the PUREX was used to recover slightly enriched uranium for recycling into fuel for use in reactors that generate electricity and plutonium. Section 2.0 provides further details of the PUREX`s physical plant and its operations. The PUREX Plant functions that generate solid waste are as follows: processing operations, laboratory analyses and supporting activities. The types and estimated quantities of waste resulting from these activities are discussed in detail.

Pottmeyer, J.A.; Weyns, M.I.; Lorenzo, D.S.; Vejvoda, E.J. [Los Alamos Technical Associates, Inc., NM (US); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (US)

1993-04-01T23:59:59.000Z

85

Solid radioactive waste management facility design for managing CANDU{sup R} 600 MW nuclear generating station re-tube/refurbishment Waste Streams  

Science Conference Proceedings (OSTI)

The main design features of the re-tube canisters, waste handling equipment and waste containers designed by Atomic Energy of Canada Limited (AECL{sup R}) and implemented in support of the re-tube/refurbishment activities for Candu 600 MW nuclear generating stations are described in this paper. The re-tube/refurbishment waste characterization and the waste management principles, which form the basis of the design activities, are also briefly outlined. (authors)

Pontikakis, N.; Hopkins, J.; Scott, D.; Bajaj, V.; Nosella, L. [AECL, 2251 Speakman Drive, Mississauga, Ontario, L5K 1B2 (Canada)

2007-07-01T23:59:59.000Z

86

Waste Isolation Pilot Plant Transuranic Waste Baseline inventory report. Volume 2. Revision 1  

SciTech Connect

This document is the Baseline Inventory Report for the transuranic (alpha-bearing) wastes stored at the Waste Isolation Pilot Plant (WIPP) in New Mexico. Waste stream profiles including origin, applicable EPA codes, typical isotopic composition, typical waste densities, and typical rates of waste generation for each facility are presented for wastes stored at the WIPP.

1995-02-01T23:59:59.000Z

87

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...

88

Secondary Waste Cast Stone Waste Form Qualification Testing Plan  

SciTech Connect

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

Westsik, Joseph H.; Serne, R. Jeffrey

2012-09-26T23:59:59.000Z

89

CLAB Transuranic Waste Spreadsheets  

Science Conference Proceedings (OSTI)

The Building 772-F Far-Field Transuranic (TRU) Waste Counting System is used to measure the radionuclide content of waste packages produced at the Central Laboratory Facilities (CLAB). Data from the instrument are entered into one of two Excel spreadsheets. The waste stream associated with the waste package determines which spreadsheet is actually used. The spreadsheets calculate the necessary information required for completion of the Transuranic Waste Characterization Form (OSR 29-90) and the Radioactive Solid Waste Burial Ground Record (OSR 7-375 or OSR 7-375A). In addition, the spreadsheets calculate the associated Low Level Waste (LLW) stream information that potentially could be useful if the waste container is ever downgraded from TRU to LLW. The spreadsheets also have the capability to sum activities from source material added to a waste container after assay. A validation data set for each spreadsheet along with the appropriate results are also presented in this report for spreadsheet verification prior to each use.

Leyba, J.D.

2000-08-11T23:59:59.000Z

90

Waste= Capital.  

E-Print Network (OSTI)

??The evolution of manufacturing practices over the last century has led to the creation of excess waste during the production process, depleting resources and overwhelming… (more)

Stidham, Steve P.

2011-01-01T23:59:59.000Z

91

Novel selective surface flow (SSF{sup TM}) membranes for the recovery of hydrogren from waste gas streams. Final report  

DOE Green Energy (OSTI)

The waste streams are off-gas streams from various chemical/refinery operations. In Phase I, the architecture of the membrane and the separation device were defined and demonstrated. The system consists of a shell-and-tube separator in which the gas to be separated is fed to the tube side, the product is collected as high pressure effluent and the permeate constitutes the waste/fuel stream. Each tube, which has the membrane coated on the interior, does the separation. A multi- tube separator device containing 1 ft{sup 2} membrane area was built and tested. The engineering data were used for designing a process for hydrogen recovery from a fluid catalytic cracker off-gas stream. First-pass economics showed that overall cost for hydrogen production is reduced by 35% vs on-purpose production of hydrogen by steam- methane reforming. The hydrogen recovery process using the SSF membrane results in at least 15% energy reduction and significant decrease in CO{sub 2} and NO{sub x} emissions.

Anand, M. [USDOE, Washington, DC (United States)

1995-08-01T23:59:59.000Z

92

Session 35 - Panel: Remaining US Disposition Issues for Orphan or Small Volume Low Level and Low Level Mixed Waste Streams  

Science Conference Proceedings (OSTI)

Faced with closure schedules as a driving force, significant progress has been made during the last 2 years on the disposition of DOE mixed waste streams thought previously to be problematic. Generators, the Department of Energy and commercial vendors have combined to develop unique disposition paths for former orphan streams. Recent successes and remaining issues will be discussed. The session will also provide an opportunity for Federal agencies to share lessons learned on low- level and mixed low-level waste challenges and identify opportunities for future collaboration. This panel discussion was organized by PAC member Dick Blauvelt, Navarro Research and Engineering Inc who served as co-chair along with Dave Eaton from INL. In addition, George Antonucci, Duratek Barnwell and Rich Conley, AFSC were invited members of the audience, prepared to contribute the Barnwell and DOD perspective to the issues as needed. Mr. Small provide information regarding the five year 20K M3 window of opportunity at the Nevada Test Site for DOE contractors to dispose of mixed waste that cannot be received at the Energy Solutions (Envirocare) site in Utah because of activity levels. He provided a summary of the waste acceptance criteria and the process sites must follow to be certified to ship. When the volume limit or time limit is met, the site will undergo a RCRA closure. Ms. Gelles summarized the status of the orphan issues, commercial options and the impact of the EM reorganization on her program. She also announced that there would be a follow-on meeting in 2006 to the very successful St. Louis meeting of last year. It will probably take place in Chicago in July. Details to be announced. Mr. McKenney discussed progress made at the Hanford Reservation regarding disposal of their mixed waste inventory. The news is good for the Hanford site but not good for the rest of the DOE complex since shipment for out of state of both low level and low level mixed waste will continue to be prohibited until the completion of a new NEPA study. This is anticipated to take several years. Bill Franz from Portsmouth and Dave Eaton representing the INL provided the audience with information regarding some of the problematic mixed waste streams at their respective sites. Portsmouth has some unique radiological issues with isotopes such as Tc-99 while the INL is trying to deal with mixed waste in the 10-100 nCi/g range. Kaylin Loveland spoke of the new,Energy Solutions organization and provided information on mixed waste treatment capabilities at the Clive site. Mike Lauer described the licensing activities at the WCS site in Texas where they are trying to eventually have disposal capabilities for Class A, B and C mixed waste from both DOE and the commercial sector. The audience included about 75 WM'06 attendees who asked some excellent questions and provided an active and informative exchange of information on the topic. (authors)

Blauvelt, Richard [Navarro Engineering Research Inc. (United States); Small, Ken [Doe Nevada (United States); Gelles, Christine [DOE EM HQ (United States); McKenney, Dale [Fluor Hanford (United States); Franz, Bill [LATA Portsmouth (United States); Loveland, Kaylin [Energy Solutions Inc. (United States); Lauer, Mike [Waste Control Specialists (United States)

2006-07-01T23:59:59.000Z

93

Laboratory Waste Disposal HAZARDOUS GLASS  

E-Print Network (OSTI)

Laboratory Waste Disposal HAZARDOUS GLASS Items that could cut or puncture skin or trash- can liners. This waste stream must be boxed to protect custodial staff. It goes directly to the landfill lined cardboard box. Tape seams with heavy duty tape to contain waste. Limit weight to 20 lbs. Or

Sheridan, Jennifer

94

MUSHROOM WASTE MANAGEMENT PROJECT LIQUID WASTE MANAGEMENT  

E-Print Network (OSTI)

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

95

Materials and Energy Recovery from the Dry Stream of New York City's Municipal Solid Waste  

E-Print Network (OSTI)

from waste and significant reductions of material that must be sent to a landfill. 4.1.5 Co-Firing, another advantage of co-firing emerges. The addition of CS to coal in a power plant may lower some. Several plants in the United States have tried this combination with varying degrees of success. The co-firing

Columbia University

96

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE  

E-Print Network (OSTI)

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE January 2010 Prepared for the Interagency DE-AC05-76RL01830 Waste Disposal Workshops: Anthrax-Contaminated Waste AM Lesperance JF Upton SL #12;#12;PNNL-SA-69994 Waste Disposal Workshops: Anthrax- Contaminated Waste AM Lesperance JF Upton SL

97

Special Analysis for the Disposal of the Consolidated Edison Uranium Solidification Project Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada  

Science Conference Proceedings (OSTI)

The purpose of this Special Analysis (SA) is to determine if the Oak Ridge (OR) Consolidated Edison Uranium Solidification Project (CEUSP) uranium-233 (233U) waste stream (DRTK000000050, Revision 0) is acceptable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). The CEUSP 233U waste stream requires a special analysis because the concentrations of thorium-229 (229Th), 230Th, 232U, 233U, and 234U exceeded their NNSS Waste Acceptance Criteria action levels. The acceptability of the waste stream is evaluated by determining if performance assessment (PA) modeling provides a reasonable expectation that SLB disposal is protective of human health and the environment. The CEUSP 233U waste stream is a long-lived waste with unique radiological hazards. The SA evaluates the long-term acceptability of the CEUSP 233U waste stream for near-surface disposal as a two tier process. The first tier, which is the usual SA process, uses the approved probabilistic PA model to determine if there is a reasonable expectation that disposal of the CEUSP 233U waste stream can meet the performance objectives of U.S. Department of Energy Manual DOE M 435.1-1, “Radioactive Waste Management,” for a period of 1,000 years (y) after closure. The second tier addresses the acceptability of the OR CEUSP 233U waste stream for near-surface disposal by evaluating long-term site stability and security, by performing extended (i.e., 10,000 and 60,000 y) modeling analyses, and by evaluating the effect of containers and the depth of burial on performance. Tier I results indicate that there is a reasonable expectation of compliance with all performance objectives if the OR CEUSP 233U waste stream is disposed in the Area 5 RWMS SLB disposal units. The maximum mean and 95th percentile PA results are all less than the performance objective for 1,000 y. Monte Carlo uncertainty analysis indicates that there is a high likelihood of compliance with all performance objectives. Tier II results indicate that the long-term performance of the OR CEUSP 233U waste stream is protective of human health and the environment. The Area 5 RWMS is located in one of the least populated and most arid regions of the U.S. Site characterization data indicate that infiltration of precipitation below the plant root zone at 2.5 meters (8.2 feet) ceased 10,000 to 15,000 y ago. The site is not expected to have a groundwater pathway as long as the current arid climate persists. The national security mission of the NNSS and the location of the Area 5 RWMS within the Frenchman Flat Corrective Action Unit require that access controls and land use restrictions be maintained indefinitely. PA modeling results for 10,000 to 60,000 y also indicate that the OR CEUSP 233U waste stream is acceptable for near-surface disposal. The mean resident air pathway annual total effective dose (TED), the resident all-pathways annual TED, and the acute drilling TED are less than their performance objectives for 10,000 y after closure. The mean radon-222 (222Rn) flux density exceeds the performance objective at 4,200 y, but this is due to waste already disposed at the Area 5 RWMS and is only slightly affected by disposal of the CEUSP 233U. The peak resident all-pathways annual TED from CEUSP key radionuclides occurs at 48,000 y and is less than the 0.25 millisievert performance objective. Disposal of the OR CEUSP 233U waste stream in a typical SLB trench slightly increases PA results. Increasing the depth was found to eliminate any impacts of the OR CEUSP 233U waste stream. Containers could not be shown to have any significant impact on performance due to the long half-life of the waste stream and a lack of data for pitting corrosion rates of stainless steel in soil. The results of the SA indicate that all performance objectives can be met with disposal of the OR CEUSP 233U waste stream in the SLB units at the Area 5 RWMS. The long-term performance of the OR CEUSP 233U waste stream disposed in the near surface is protective of human health

NSTec Environmental Management

2013-01-31T23:59:59.000Z

98

Special Analysis for the Disposal of the Consolidated Edison Uranium Solidification Project Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada  

SciTech Connect

The purpose of this Special Analysis (SA) is to determine if the Oak Ridge (OR) Consolidated Edison Uranium Solidification Project (CEUSP) uranium-233 (233U) waste stream (DRTK000000050, Revision 0) is acceptable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). The CEUSP 233U waste stream requires a special analysis because the concentrations of thorium-229 (229Th), 230Th, 232U, 233U, and 234U exceeded their NNSS Waste Acceptance Criteria action levels. The acceptability of the waste stream is evaluated by determining if performance assessment (PA) modeling provides a reasonable expectation that SLB disposal is protective of human health and the environment. The CEUSP 233U waste stream is a long-lived waste with unique radiological hazards. The SA evaluates the long-term acceptability of the CEUSP 233U waste stream for near-surface disposal as a two tier process. The first tier, which is the usual SA process, uses the approved probabilistic PA model to determine if there is a reasonable expectation that disposal of the CEUSP 233U waste stream can meet the performance objectives of U.S. Department of Energy Manual DOE M 435.1-1, “Radioactive Waste Management,” for a period of 1,000 years (y) after closure. The second tier addresses the acceptability of the OR CEUSP 233U waste stream for near-surface disposal by evaluating long-term site stability and security, by performing extended (i.e., 10,000 and 60,000 y) modeling analyses, and by evaluating the effect of containers and the depth of burial on performance. Tier I results indicate that there is a reasonable expectation of compliance with all performance objectives if the OR CEUSP 233U waste stream is disposed in the Area 5 RWMS SLB disposal units. The maximum mean and 95th percentile PA results are all less than the performance objective for 1,000 y. Monte Carlo uncertainty analysis indicates that there is a high likelihood of compliance with all performance objectives. Tier II results indicate that the long-term performance of the OR CEUSP 233U waste stream is protective of human health and the environment. The Area 5 RWMS is located in one of the least populated and most arid regions of the U.S. Site characterization data indicate that infiltration of precipitation below the plant root zone at 2.5 meters (8.2 feet) ceased 10,000 to 15,000 y ago. The site is not expected to have a groundwater pathway as long as the current arid climate persists. The national security mission of the NNSS and the location of the Area 5 RWMS within the Frenchman Flat Corrective Action Unit require that access controls and land use restrictions be maintained indefinitely. PA modeling results for 10,000 to 60,000 y also indicate that the OR CEUSP 233U waste stream is acceptable for near-surface disposal. The mean resident air pathway annual total effective dose (TED), the resident all-pathways annual TED, and the acute drilling TED are less than their performance objectives for 10,000 y after closure. The mean radon-222 (222Rn) flux density exceeds the performance objective at 4,200 y, but this is due to waste already disposed at the Area 5 RWMS and is only slightly affected by disposal of the CEUSP 233U. The peak resident all-pathways annual TED from CEUSP key radionuclides occurs at 48,000 y and is less than the 0.25 millisievert performance objective. Disposal of the OR CEUSP 233U waste stream in a typical SLB trench slightly increases PA results. Increasing the depth was found to eliminate any impacts of the OR CEUSP 233U waste stream. Containers could not be shown to have any significant impact on performance due to the long half-life of the waste stream and a lack of data for pitting corrosion rates of stainless steel in soil. The results of the SA indicate that all performance objectives can be met with disposal of the OR CEUSP 233U waste stream in the SLB units at the Area 5 RWMS. The long-term performance of the OR CEUSP 233U waste stream disposed in the near surface is protective of human health

NSTec Environmental Management

2013-01-31T23:59:59.000Z

99

Feed Materials Production Center Waste Management Plan  

SciTech Connect

In the process of producing uranium metal products used in Department of Energy (DOE) defense programs at other DOE facilities, various types of wastes are generated at the Feed Materials Production Center (FMPC). Process wastes, both generated and stored, are discussed in the Waste Management Plan and include low-level radioactive waste (LLW), mixed hazardous/radioactive waste, and sanitary/industrial waste. Scrap metal waste and wastes requiring special remediation are also addressed in the Plan. The Waste Management Plan identifies the comprehensive programs developed to address safe storage and disposition of all wastes from past, present, and future operations at the FMPC. Waste streams discussed in this Plan are representative of the waste generated and waste types that concern worker and public health and safety. Budgets and schedules for implementation of waste disposition are also addressed. The waste streams receiving the largest amount of funding include LLW approved for shipment by DOE/ORO to the Nevada Test Site (NTS) (MgF/sub 2/, slag leach filter cake, and neutralized raffinate); remedial action wastes (waste pits, K-65 silo waste); thorium; scrap metal (contaminated and noncontaminated ferrous and copper scrap); construction rubble and soil generated from decontamination and decommissioning of outdated facilities; and low-level wastes that will be handled through the Low-Level Waste Processing and Shipping System (LLWPSS). Waste Management milestones are also provided. The Waste Management Plan is divided into eight major sections: Introduction; Site Waste and Waste Generating Process; Strategy; Projects and Operations; Waste Stream Budgets; Milestones; Quality Assurance for Waste Management; and Environmental Monitoring Program.

Watts, R.E.; Allen, T.; Castle, S.A.; Hopper, J.P.; Oelrich, R.L.

1986-12-31T23:59:59.000Z

100

Selective partitioning of mercury from co-extracted actinides in a simulated acidic ICPP waste stream  

SciTech Connect

The TRUEX process is being evaluated at the Idaho Chemical Processing Plant (ICPP) as a means to partition the actinides from acidic sodium-bearing waste (SBW). The mercury content of this waste averages 1 g/l. Because the chemistry of mercury has not been extensively evaluated in the TRUEX process, mercury was singled out as an element of interest. Radioactive mercury, {sup 203}Hg, was spiked into a simulated solution of SBW containing 1 g/l mercury. Successive extraction batch contacts with the mercury spiked waste simulant and successive scrubbing and stripping batch contacts of the mercury loaded TRUEX solvent (0.2 M CMPO-1.4 M TBP in dodecane) show that mercury will extract into and strip from the solvent. The extraction distribution coefficient for mercury, as HgCl{sub 2} from SBW having a nitric acid concentration of 1.4 M and a chloride concentration of 0.035 M was found to be 3. The stripping distribution coefficient was found to be 0.5 with 5 M HNO{sub 3} and 0.077 with 0.25 M Na{sub 2}CO{sub 3}. An experimental flowsheet was designed from the batch contact tests and tested counter-currently using 5.5 cm centrifugal contactors. Results from the counter-current test show that mercury can be removed from the acidic mixed SBW simulant and recovered separately from the actinides.

Brewer, K.N.; Herbst, R.S.; Tranter, T.J. [and others

1995-12-01T23:59:59.000Z

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

Waste Hoist  

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

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

102

Vitrification of hazardous and radioactive wastes  

SciTech Connect

Vitrification offers many attractive waste stabilization options. Versatility of waste compositions, as well as the inherent durability of a glass waste form, have made vitrification the treatment of choice for high-level radioactive wastes. Adapting the technology to other hazardous and radioactive waste streams will provide an environmentally acceptable solution to many of the waste challenges that face the public today. This document reviews various types and technologies involved in vitrification.

Bickford, D.F.; Schumacher, R.

1995-12-31T23:59:59.000Z

103

Advanced Electrochemical Waste Forms  

Science Conference Proceedings (OSTI)

... of Fluidized Bed Steam Reforming (FBSR) with Hanford Low Activity Wastes ... Level Waste at the Defense Waste Processing Facility through Sludge Batch 7b.

104

Using Biosurfactants Produced from Agriculture Process Waste Streams to Improve Oil Recovery in Fractured Carbonate Reservoirs  

Science Conference Proceedings (OSTI)

This report describes the progress of our research during the first 30 months (10/01/2004 to 03/31/2007) of the original three-year project cycle. The project was terminated early due to DOE budget cuts. This was a joint project between the Tertiary Oil Recovery Project (TORP) at the University of Kansas and the Idaho National Laboratory (INL). The objective was to evaluate the use of low-cost biosurfactants produced from agriculture process waste streams to improve oil recovery in fractured carbonate reservoirs through wettability mediation. Biosurfactant for this project was produced using Bacillus subtilis 21332 and purified potato starch as the growth medium. The INL team produced the biosurfactant and characterized it as surfactin. INL supplied surfactin as required for the tests at KU as well as providing other microbiological services. Interfacial tension (IFT) between Soltrol 130 and both potential benchmark chemical surfactants and crude surfactin was measured over a range of concentrations. The performance of the crude surfactin preparation in reducing IFT was greater than any of the synthetic compounds throughout the concentration range studied but at low concentrations, sodium laureth sulfate (SLS) was closest to the surfactin, and was used as the benchmark in subsequent studies. Core characterization was carried out using both traditional flooding techniques to find porosity and permeability; and NMR/MRI to image cores and identify pore architecture and degree of heterogeneity. A cleaning regime was identified and developed to remove organic materials from cores and crushed carbonate rock. This allowed cores to be fully characterized and returned to a reproducible wettability state when coupled with a crude-oil aging regime. Rapid wettability assessments for crushed matrix material were developed, and used to inform slower Amott wettability tests. Initial static absorption experiments exposed limitations in the use of HPLC and TOC to determine surfactant concentrations. To reliably quantify both benchmark surfactants and surfactin, a surfactant ion-selective electrode was used as an indicator in the potentiometric titration of the anionic surfactants with Hyamine 1622. The wettability change mediated by dilute solutions of a commercial preparation of SLS (STEOL CS-330) and surfactin was assessed using two-phase separation, and water flotation techniques; and surfactant loss due to retention and adsorption on the rock was determined. Qualitative tests indicated that on a molar basis, surfactin is more effective than STEOL CS-330 in altering wettability of crushed Lansing-Kansas City carbonates from oil-wet to water-wet state. Adsorption isotherms of STEOL CS-330 and surfactin on crushed Lansing-Kansas City outcrop and reservoir material showed that surfactin has higher specific adsorption on these oomoldic carbonates. Amott wettability studies confirmed that cleaned cores are mixed-wet, and that the aging procedure renders them oil-wet. Tests of aged cores with no initial water saturation resulted in very little spontaneous oil production, suggesting that water-wet pathways into the matrix are required for wettability change to occur. Further investigation of spontaneous imbibition and forced imbibition of water and surfactant solutions into LKC cores under a variety of conditions--cleaned vs. crude oil-aged; oil saturated vs. initial water saturation; flooded with surfactant vs. not flooded--indicated that in water-wet or intermediate wet cores, sodium laureth sulfate is more effective at enhancing spontaneous imbibition through wettability change. However, in more oil-wet systems, surfactin at the same concentration performs significantly better.

Stephen Johnson; Mehdi Salehi; Karl Eisert; Sandra Fox

2009-01-07T23:59:59.000Z

105

Use of thermal analysis techniques (TG-DSC) for the characterization of diverse organic municipal waste streams to predict biological stability prior to land application  

Science Conference Proceedings (OSTI)

Highlights: Black-Right-Pointing-Pointer Thermal analysis was used to assess stability and composition of organic matter in three diverse municipal waste streams. Black-Right-Pointing-Pointer Results were compared with C mineralization during 90-day incubation, FTIR and {sup 13}C NMR. Black-Right-Pointing-Pointer Thermal analysis reflected the differences between the organic wastes before and after the incubation. Black-Right-Pointing-Pointer The calculated energy density showed a strong correlation with cumulative respiration. Black-Right-Pointing-Pointer Conventional and thermal methods provide complimentary means of characterizing organic wastes. - Abstract: The use of organic municipal wastes as soil amendments is an increasing practice that can divert significant amounts of waste from landfill, and provides a potential source of nutrients and organic matter to ameliorate degraded soils. Due to the high heterogeneity of organic municipal waste streams, it is difficult to rapidly and cost-effectively establish their suitability as soil amendments using a single method. Thermal analysis has been proposed as an evolving technique to assess the stability and composition of the organic matter present in these wastes. In this study, three different organic municipal waste streams (i.e., a municipal waste compost (MC), a composted sewage sludge (CS) and a thermally dried sewage sludge (TS)) were characterized using conventional and thermal methods. The conventional methods used to test organic matter stability included laboratory incubation with measurement of respired C, and spectroscopic methods to characterize chemical composition. Carbon mineralization was measured during a 90-day incubation, and samples before and after incubation were analyzed by chemical (elemental analysis) and spectroscopic (infrared and nuclear magnetic resonance) methods. Results were compared with those obtained by thermogravimetry (TG) and differential scanning calorimetry (DSC) techniques. Total amounts of CO{sub 2} respired indicated that the organic matter in the TS was the least stable, while that in the CS was the most stable. This was confirmed by changes detected with the spectroscopic methods in the composition of the organic wastes due to C mineralization. Differences were especially pronounced for TS, which showed a remarkable loss of aliphatic and proteinaceous compounds during the incubation process. TG, and especially DSC analysis, clearly reflected these differences between the three organic wastes before and after the incubation. Furthermore, the calculated energy density, which represents the energy available per unit of organic matter, showed a strong correlation with cumulative respiration. Results obtained support the hypothesis of a potential link between the thermal and biological stability of the studied organic materials, and consequently the ability of thermal analysis to characterize the maturity of municipal organic wastes and composts.

Fernandez, Jose M., E-mail: joseman@sas.upenn.edu [Department of Earth and Environmental Science, University of Pennsylvania, Philadelphia, PA 19104-6316 (United States); Plaza, Cesar; Polo, Alfredo [Instituto de Ciencias Agrarias, Consejo Superior de Investigaciones Cientificas, Serrano 115 dpdo., 28006 Madrid (Spain); Plante, Alain F. [Department of Earth and Environmental Science, University of Pennsylvania, Philadelphia, PA 19104-6316 (United States)

2012-01-15T23:59:59.000Z

106

Understanding Cement Waste Forms  

Science Conference Proceedings (OSTI)

Oct 29, 2009 ... Ongoing nuclear operations, decontamination and decommissioning, salt waste disposal, and closure of liquid waste tanks result in ...

107

Waste Minimization Contents  

Science Conference Proceedings (OSTI)

About the 1996 International Symposium on Extraction and Processing for the Treatment and Minimization of Wastes: Waste Minimization Contents ...

108

Method for sequestering CO.sub.2 and SO.sub.2 utilizing a plurality of waste streams  

DOE Patents (OSTI)

A neutralization/sequestration process is provided for concomitantly addressing capture and sequestration of both CO.sub.2 and SO.sub.2 from industrial gas byproduct streams. The invented process concomitantly treats and minimizes bauxite residues from aluminum production processes and brine wastewater from oil/gas production processes. The benefits of this integrated approach to coincidental treatment of multiple industrial waste byproduct streams include neutralization of caustic byproduct such as bauxite residue, thereby decreasing the risk associated with the long-term storage and potential environmental of storing caustic materials, decreasing or obviating the need for costly treatment of byproduct brines, thereby eliminating the need to purchase CaO or similar scrubber reagents typically required for SO.sub.2 treatment of such gasses, and directly using CO.sub.2 from flue gas to neutralize bauxite residue/brine mixtures, without the need for costly separation of CO.sub.2 from the industrial byproduct gas stream by processes such as liquid amine-based scrubbers.

Soong, Yee (Monroeville, PA); Allen, Douglas E. (Salem, MA); Zhu, Chen (Monroe County, IN)

2011-04-12T23:59:59.000Z

109

Waste Disposition Update by Christine Gelles  

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

Waste Disposition Update Waste Disposition Update Christine Gelles Associate Deputy Assistant Secretary for Waste Management (EM-30) EM SSAB Chairs Meeting Washington, DC 2 October 2012 www.em.doe.gov 2 o Waste Stream Highlights o DOE Transportation Update o Greater Than Class C (GTCC) Low Level Waste Environmental Impact Statement o Blue Ribbon Commission on America's Nuclear Future o Nuclear Regulatory Commission's LLW Regulatory Initiatives Discussion Topics www.em.doe.gov 3 Waste Stream Highlights www.em.doe.gov 4 o Within current budget outlook, it is especially critical that EM ensures safe, reliable and cost effective disposition paths exist. o The program's refocused organization and the detailed

110

ICDF Complex Operations Waste Management Plan  

SciTech Connect

This Waste Management Plan functions as a management and planning tool for managing waste streams generated as a result of operations at the Idaho CERCLA Disposal Facility (ICDF) Complex. The waste management activities described in this plan support the selected remedy presented in the Waste Area Group 3, Operable Unit 3-13 Final Record of Decision for the operation of the Idaho CERCLA Disposal Facility Complex. This plan identifies the types of waste that are anticipated during operations at the Idaho CERCLA Disposal Facility Complex. In addition, this plan presents management strategies and disposition for these anticipated waste streams.

W.M. Heileson

2006-12-01T23:59:59.000Z

111

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

112

WASTE TO WATTS Waste is a Resource!  

E-Print Network (OSTI)

WASTE TO WATTS Waste is a Resource! energy forum Case Studies from Estonia, Switzerland, Germany BREFs and their BATs Next Generation of Waste Fired Power Plants: Getting the most out of your trash Bossart,· ABB Waste-to-Energy Plants Edmund Fleck,· ESWET Marcel van Berlo,· Afval Energie Bedrijf From

Columbia University

113

Vitrification of high sulfate wastes  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE) through the Mixed Waste Integrated Program (MWIP) is investigating the application of vitrification technology to mixed wastes within the DOE system This work involves identifying waste streams, laboratory testing to identify glass formulations and characterize the vitrified product, and demonstration testing with the actual waste in a pilot-scale system. Part of this program is investigating process limits for various waste components, specifically those components that typically create problems for the application of vitrification, such as sulfate, chloride, and phosphate. This work describes results from vitrification testing for a high-sulfate waste, the 183-H Solar Evaporation Basin waste at Hanford. A low melting phosphate glass formulation has been developed for a waste stream high in sodium and sulfate. At melt temperatures in the range of 1,000 C to 1,200 C, sulfate in the waste is decomposed to gaseous oxides and driven off during melting, while the remainder of the oxides stay in the melt. Decomposition of the sulfates eliminates the processing problems typically encountered in vitrification of sulfate-containing wastes, resulting in separation of the sulfate from the remainder of the waste and allowing the sulfate to be collected in the off-gas system and treated as a secondary waste stream. Both the vitreous product and intentionally devitrified samples are durable when compared to reference glasses by TCLP and DI water leach tests. Simple, short tests to evaluate the compatibility of the glasses with potential melter materials found minimal corrosion with most materials.

Merrill, R.A.; Whittington, K.F.; Peters, R.D.

1994-09-01T23:59:59.000Z

114

Waste Hoist  

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

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

115

Mr. John Kieling, Acting Chief Hazardous Waste Bureau Depa  

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

for the upcoming federal fiscal year: * SR-RL-BCLDP.001 : A Remote Handled transuranic debris waste stream This remote-handled transuranic debris waste stream consists of organic...

116

SYNTHESIS OF SULFUR-BASED WATER TREATMENT AGENT FROM SULFUR DIOXIDE WASTE STREAMS  

Science Conference Proceedings (OSTI)

Absorption of sulfur dioxide from a simulated flue gas was investigated for the production of polymeric ferric sulfate (PFS), a highly effective coagulant useful in treatment of drinking water and wastewater. The reaction for PFS synthesis took place near atmospheric pressure and at temperatures of 30-80 C. SO{sub 2} removal efficiencies greater than 90% were achieved, with ferrous iron concentrations in the product less than 0.1%. A factorial analysis of the effect of temperature, oxidant dosage, SO{sub 2} concentration, and gas flow rate on SO{sub 2} removal efficiency was carried out, and statistical analyses are conducted. The solid PFS was also characterized with different methods. Characterization results have shown that PFS possesses both crystalline and non-crystalline structure. The kinetics of reactions among FeSO{sub 4} {center_dot} 7H{sub 2}O, NaHSO{sub 3} and NaClO{sub 3} was investigated. Characterizations of dry PFS synthesized from SO{sub 2} show the PFS possesses amorphous structure, which is desired for it to be a good coagulant in water and wastewater treatment. A series of lab-scale experiments were conducted to evaluate the performance of PFS synthesized from waste sulfur dioxide, ferrous sulfate and sodium chlorate. The performance assessments were based on the comparison of PFS and other conventional and new coagulants for the removal of turbidity and arsenic under different laboratory coagulant conditions. Pilot plant studies were conducted at Des Moines Water Works in Iowa and at the City of Savannah Industrial and Domestic (I&D) Water Treatment Plant in Port Wentworth, Georgia. PFS performances were compared with those of conventional coagulants. The tests in both water treatment plants have shown that PFS is, in general, comparable or better than other coagulants in removal of turbidity and organic substances. The corrosion behavior of polymeric ferric sulfate (PFS) prepared from SO{sub 2} and ferric chloride (FC) were compared. Results showed that both temperature and concentration of the coagulants substantially impact corrosion rates. The corrosion rates increased with the increase of temperature and concentration. The results from a scanning electron microscope (SEM) showed that chloride caused more serious pitting than sulfate anion on both aluminum and steel specimens. Although SEM confirmed the existence of pitting corrosion, the results of weight loss indicated that the uniform corrosion predominate the corrosion mechanism, and pitting corrosion played a less important role. The test proved that PFS was less corrosive than FC, which may lead to the large-scale application of PFS in waste treatment. The kinetics of the new desulfurization process has been studied. The study results provide the theoretical guidance for improving sulfur removal efficiency and controlling the quality of PFS.

Robert C. Brown; Maohong Fan; Adrienne Cooper

2004-11-01T23:59:59.000Z

117

Medical School Biomedical Waste  

E-Print Network (OSTI)

Medical School Biomedical Waste Labware, gloves, pipets, pipet tips Stock cultures, bacterial with or without needles, razor blades, scalpel blades) Key: Pathological waste BL1 & BL2 waste (low risk ­ LR) BL2 waste (moderate risk - MR)/BL3 waste Blood Blood Autoclave Needle box Metal Cart Must either bleach

Cooley, Lynn

118

Waste Sorting Activity Introduction  

E-Print Network (OSTI)

Waste Sorting Activity Introduction: This waste sorting game was originally designed to be one have completed the waste sorting activity quickly, no team was able to complete the waste sorting task who were unfamiliar with Dalhousie's waste management system. Goals: The primary goal of the activity

Beaumont, Christopher

119

University of Waste Procedures  

E-Print Network (OSTI)

University of Maryland Hazardous And Regulated Waste Procedures Manual Revised July 2001 #12;Review II. HAZARDOUS WASTE MANAGEMENT III. BIOLOGICAL, PATHOLOGICAL AND MEDICAL WASTE (BPMW) MANAGEMENT IV. LOW-LEVEL RADIOACTIVE WASTE (LLRW) MANAGEMENT V. EMERGENCY PROCEDURES VI. WASTE MINIMIZATION VII

Rubloff, Gary W.

120

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

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


121

Radioactive Waste Management (Minnesota)  

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

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

122

Waste Logic Decommissioning Waste Manager 2.0 Users Manual  

Science Conference Proceedings (OSTI)

The Decommissioning Waste Manager, part of EPRI's Waste Logic series of computer programs, analyzes decommissioning waste cost and volume reduction strategies with the intent of quantifying the existing waste management program for any given waste generator.

2001-10-29T23:59:59.000Z

123

Energy Efficient Removal of Volatile Organic Compounds (VOCs) and Organic Hazardous Air Pollutants (o-HAPs) from Industrial Waste Streams by Direct Electron Oxidation  

SciTech Connect

This research program investigated and quantified the capability of direct electron beam destruction of volatile organic compounds and organic hazardous air pollutants in model industrial waste streams and calculated the energy savings that would be realized by the widespread adoption of the technology over traditional pollution control methods. Specifically, this research determined the quantity of electron beam dose required to remove 19 of the most important non-halogenated air pollutants from waste streams and constructed a technical and economic model for the implementation of the technology in key industries including petroleum refining, organic & solvent chemical production, food & beverage production, and forest & paper products manufacturing. Energy savings of 75 - 90% and green house gas reductions of 66 - 95% were calculated for the target market segments.

Testoni, A. L.

2011-10-19T23:59:59.000Z

124

Photocatalytic oxidation of gas-phase BTEX-contaminated waste streams  

Science Conference Proceedings (OSTI)

Researchers at the National Renewable Energy Laboratory (NREL) have been exploring heterogeneous photocatalytic oxidation (PCO) as a remediation technology for air streams contaminated with benzene, toluene, ethyl-benzene, and xylenes (BTEX). This research is a continuation of work performed on chlorinated organics. The photocatalytic oxidation of BTEX has been studied in the aqueous phase, however, a study by Turchi et al. showed a more economical system would involve stripping organic contaminants from the aqueous phase and treating the resulting gas stream. Another recent study by Turchi et al. indicated that PCO is cost competitive with such remediation technologies as activated carbon adsorption and catalytic incineration for some types of contaminated air streams. In this work we have examined the photocatalytic oxidation of benzene using ozone (0{sub 3}) as an additional oxidant. We varied the residence time in the PCO reactor, the initial concentration of the organic pollutant, and the initial ozone concentration in a single-pass reactor. Because aromatic hydrocarbons represent only a small fraction of the total hydrocarbons present in gasoline and other fuels, we also added octane to the reaction mixture to simulate the composition of air streams produced from soil-vapor-extraction or groundwater-stripping of sites contaminated with gasoline.

Gratson, D A; Nimlos, M R; Wolfrum, E J

1995-03-01T23:59:59.000Z

125

Solid Waste (New Mexico)  

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

The New Mexico Environment Department's Solid Waste Bureau manages solid waste in the state. The Bureau implements and enforces the rules established by the Environmental Improvement Board.

126

Industrial Waste Generation  

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

9) Page 2 of 7 Industrial Waste Generation Work with Engineered Nanomaterials Power Consumption Historical Contamination (groundwater, soil) Hazardous Waste Generation Atmospheric...

127

Recycling Electronic Waste - Website  

Science Conference Proceedings (OSTI)

Jun 18, 2010 ... Joined: 2/13/2007. Below is a link to a website that has articles on recycling electronic waste. http://www.scientificamerican....ectronic-waste- ...

128

International Trade with Waste.  

E-Print Network (OSTI)

?? In this thesis, trade with waste between developed countries and the third world will be presented to analyze whether waste?trading can create a possible… (more)

Willén, Jenny

2008-01-01T23:59:59.000Z

129

FINAL REPORT FOR THE REDUCTION OF CHROME (VI) TO CHROME (III) IN THE SECONDARY WASTE STREAM OF THE EFFLUENT TREATMENT FACILITY  

SciTech Connect

This report documents the laboratory results of RPP-PLAN-35958, Test Plan for the Effluent Treatment Facility to Reduce Chrome (VI) to Chrome (III) in the Secondary Waste Stream With the exception of the electrochemical corrosion scans, all work was carried out at the Center for Laboratory Science (CLS) located at the Columbia Basin College. This document summarizes the work carried out at CLS and includes the electrochemical scans and associated corrosion rates for 304 and 316L stainless steel.

DUNCAN JB; GUTHRIE MD

2008-08-29T23:59:59.000Z

130

Waste Heat Recovery in Industrial Facilities  

Science Conference Proceedings (OSTI)

Low-temperature waste heat streams account for the majority of the industrial waste heat inventory. With a reference temperature of 60°F (16°C), 65% of the waste heat is below 450°F (232°C) and 99% is below 1,200°F (649°C). With a reference temperature of 300°F (149°C), 14% of the waste heat is below 450°F, and 96% is below 1,200°F. Waste heat is concentrated in a few industrial manufacturing sectors. Based on a review of 21 manufacturing sectors, the top two sectors that produce waste heat are petroleu...

2010-12-20T23:59:59.000Z

131

Waste analysis plan for central waste complex  

SciTech Connect

This waste analysis plan (WAP) has been prepared for the Central Waste Complex which is located in the 200 West Area of the Hanford Facility, Richland, Washington. This WAP documents the methods used to characterize, and obtain and analyze representative samples of waste managed at this unit.

Weston, N.L.

1996-09-20T23:59:59.000Z

132

Hanford Site annual dangerous waste report: Volume 4, Waste Management Facility report, Radioactive mixed waste  

SciTech Connect

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

NONE

1994-12-31T23:59:59.000Z

133

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

Science Conference Proceedings (OSTI)

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

NONE

1994-12-31T23:59:59.000Z

134

WIMS - Waste Information Management System  

Office of Environmental Management (EM)

Welcome To WIMS Welcome To WIMS Waste Information Management System WIMS new web address: http://www.emwims.org WIMS is developed to provide DOE Headquarters and site waste managers with the tools necessary to easily visualize, understand, and manage the vast volumes, categories, and problems of forecasted waste streams. WIMS meets this need by providing a user-friendly online system to gather, organize, and present waste forecast data from DOE sites. This system provides a method for identification of waste forecast volumes, material classes, disposition pathways, and potential choke points and barriers to final disposition. Disclaimer: Disposition facility information presented is for planning purposes only and does not represent DOE's decisions or commitments. Any selection of disposition facility will be made after technical, economic, and policy considerations.

135

Infectious waste feed system  

DOE Patents (OSTI)

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

Coulthard, E. James (York, PA)

1994-01-01T23:59:59.000Z

136

Understanding radioactive waste  

SciTech Connect

This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes). (ATT)

Murray, R.L.

1981-12-01T23:59:59.000Z

137

Nuclear waste solidification  

DOE Patents (OSTI)

High level liquid waste solidification is achieved on a continuous basis by atomizing the liquid waste and introducing the atomized liquid waste into a reaction chamber including a fluidized, heated inert bed to effect calcination of the atomized waste and removal of the calcined waste by overflow removal and by attrition and elutriation from the reaction chamber, and feeding additional inert bed particles to the fluidized bed to maintain the inert bed composition.

Bjorklund, William J. (Richland, WA)

1977-01-01T23:59:59.000Z

138

Direct conversion of halogen-containing wastes to borosilicate glass  

SciTech Connect

Glass has become a preferred waste form worldwide for radioactive wastes: however, there are limitations. Halogen-containing wastes can not be converted to glass because halogens form poor-quality waste glasses. Furthermore, halides in glass melters often form second phases that create operating problems. A new waste vitrification process, the Glass Material Oxidation and dissolution System (GMODS), removes these limitations by converting halogen-containing wastes into borosilicate glass and a secondary, clean, sodium-halide stream.

Forsberg, C.W.; Beahm, E.C.; Rudolph, J.C.

1996-12-09T23:59:59.000Z

139

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

SciTech Connect

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

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

1992-09-01T23:59:59.000Z

140

Solid Waste Disposal, Hazardous Waste Management Act, Underground...  

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

Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) Eligibility...

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

Business Plan : Residential Solid Waste Collection.  

E-Print Network (OSTI)

??Residential solid waste means all the solid wastes produced in household level, which includes bio-waste, metal, mixed wastes, organic and inorganic waste. The inability of… (more)

Mazengo, Dorice

2013-01-01T23:59:59.000Z

142

Waste Management Quality Assurance Plan  

E-Print Network (OSTI)

Raya James Johnson Rad/Mixed Waste** Steve Bakhtiar – Leadhazardous, radioactive, and mixed waste at the Hazardoustraining. Radioactive and mixed waste generators must take

Waste Management Group

2006-01-01T23:59:59.000Z

143

Waste Minimization Plan Prepared by  

E-Print Network (OSTI)

Waste Minimization Plan Prepared by: Environmental Health and Safety Department Revised February 2012 #12;Waste Minimization Plan Table of Contents Policy Statement........................................................... 3 Centralized Waste Management Program

144

Hazardous Waste Act (New Mexico)  

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

"Hazardous waste" means any solid waste or combination of solid wastes that because of their quantity, concentration or physical, chemical or infectious characteristics may:  cause or significantly...

145

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

SciTech Connect

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

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

2011-09-12T23:59:59.000Z

146

NATURE OF RADIOACTIVE WASTES  

SciTech Connect

The integrated processes of nuclear industry are considered to define the nature of wastes. Processes for recovery and preparation of U and Th fuels produce wastes containing concentrated radioactive materials which present problems of confinement and dispersal. Fundamentals of waste treatment are considered from the standpoint of processes in which radioactive materials become a factor such as naturally occurring feed materials, fission products, and elements produced by parasitic neutron capture. In addition, the origin of concentrated fission product wastes is examined, as well as characteristics of present wastes and the level of fission products in wastes. Also, comments are included on high-level wastes from processes other than solvent extraction, active gaseous wastes, and low- to intermediate-level liquid wastes. (J.R.D.)

Culler, F.L. Jr.

1959-01-26T23:59:59.000Z

147

CRYSTALLINE CERAMIC WASTE FORMS: REFERENCE FORMULATION REPORT  

Science Conference Proceedings (OSTI)

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 successfully produced from a melting and crystallization process. The objective of this report is to explain the design of ceramic host systems culminating in a reference ceramic formulation for use in subsequent studies on process optimization and melt property data assessment in support of FY13 melter demonstration testing. The waste stream used as the basis for the development and testing is 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. In addition to the combined CS/LN/TM High Mo waste stream, variants without Mo and without Mo and Zr were also evaluated. Based on the results of fabricating and characterizing several simulated ceramic waste forms, two reference ceramic waste form compositions are recommended in this report. The first composition targets the CS/LN/TM combined waste stream with and without Mo. The second composition targets with CS/LN/TM combined waste stream with Mo and Zr removed. Waste streams that contain Mo must be produced in reducing environments to avoid Cs-Mo oxide phase formation. Waste streams without Mo have the ability to be melt processed in air. A path forward for further optimizing the processing steps needed to form the targeted phase assemblages is outlined in this report. Processing modifications including melting in a reducing atmosphere, and controlled heat treatment schedules are anticipated to improve the targeted elemental partitioning.

Brinkman, K.; Fox, K.; Marra, J.

2012-05-15T23:59:59.000Z

148

Acceptable Knowledge Summary Report for Waste Stream: SR-T001-221F-HET/Drums  

Science Conference Proceedings (OSTI)

This report is fully responsive to the requirements of Section 4.0 Acceptable Knowledge from the WIPP Transuranic Waste Characterization Quality Assurance Plan, CAO-94-1010, and provides a sound, (and auditable) characterization that satisfies the WIPP criteria for Acceptable Knowledge.

Lunsford, G.F.

1999-06-14T23:59:59.000Z

149

Waste Management Facilities Cost Information Report  

Science Conference Proceedings (OSTI)

The Waste Management Facility Cost Information (WMFCI) Report, commissioned by the US Department of Energy (DOE), develops planning life-cycle cost (PLCC) estimates for treatment, storage, and disposal facilities. This report contains PLCC estimates versus capacity for 26 different facility cost modules. A procedure to guide DOE and its contractor personnel in the use of estimating data is also provided. Estimates in the report apply to five distinctive waste streams: low-level waste, low-level mixed waste, alpha contaminated low-level waste, alpha contaminated low-level mixed waste, and transuranic waste. The report addresses five different treatment types: incineration, metal/melting and recovery, shredder/compaction, solidification, and vitrification. Data in this report allows the user to develop PLCC estimates for various waste management options.

Feizollahi, F.; Shropshire, D.

1992-10-01T23:59:59.000Z

150

Waste2Energy Holdings | Open Energy Information  

Open Energy Info (EERE)

Holdings Holdings Jump to: navigation, search Name Waste2Energy Holdings Place Greenville, South Carolina Zip 29609 Sector Biomass, Renewable Energy Product The Waste2Energy Holdings is a supplier of proprietary gasification technology designed to convert municipal solid waste, biomass and other solid waste streams traditionally destined for landfill into clean renewable energy. References Waste2Energy Holdings[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Waste2Energy Holdings is a company located in Greenville, South Carolina . References ↑ "Waste2Energy Holdings" Retrieved from "http://en.openei.org/w/index.php?title=Waste2Energy_Holdings&oldid=352938

151

Mixed and Low-Level Waste Treatment Facility project  

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

152

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect

As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package (TRUPACT-11 SARP). In addition, a TRU waste is eligible for disposal at WIPP only if it has been generated in whole or in part by one or more of the activities listed in Section 10101(3) of the Nuclear Waste Policy Act. DOE sites must determine that each waste stream to be disposed of at WIPP is ''defense'' TRU waste. (See also the definition of ''defense'' TRU waste.). Only CH TRU wastes meeting the requirements of the QAPjP, WIPP-WAP, WPP-WAC, and other requirements documents described above will be accepted for transportation and disposal at WIPP.

GREAGER, T.M.

2000-12-01T23:59:59.000Z

153

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect

As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package (TRUPACT-11 SARP). In addition, a TRU waste is eligible for disposal at WIPP only if it has been generated in whole or in part by one or more of the activities listed in Section 10101(3) of the Nuclear Waste Policy Act. DOE sites must determine that each waste stream to be disposed of at WIPP is ''defense'' TRU waste. (See also the definition of ''defense'' TRU waste.). Only CH TRU wastes meeting the requirements of the QAPjP, WIPP-WAP, WPP-WAC, and other requirements documents described above will be accepted for transportation and disposal at WIPP.

GREAGER, T.M.

2000-12-06T23:59:59.000Z

154

Waste Utilization  

Science Conference Proceedings (OSTI)

Mar 14, 2012 ... The article studies the fluoride content in a stream of the Pearl River of China. The fluoride concentration is excessive all the time in this strenm, ...

155

Development of Cementitious Waste Forms for Nuclear Waste ...  

Science Conference Proceedings (OSTI)

Symposium, Materials Solutions for the Nuclear Renaissance. Presentation Title, Development of Cementitious Waste Forms for Nuclear Waste Immobilization.

156

Sulfur polymer cement for macroencapsulation of mixed waste debris  

SciTech Connect

In FY 1997, the US DOE Mixed Waste Focus Area (MWFA) sponsored a demonstration of the macroencapsulation of mixed waste debris using sulfur polymer cement (SPC). Two mixed wastes were tested--a D006 waste comprised of sheets of cadmium and a D008/D009 waste comprised of lead pipes and joints contaminated with mercury. The demonstration was successful in rendering these wastes compliant with Land Disposal Restrictions (LDR), thereby eliminating one Mixed Waste Inventory Report (MWIR) waste stream from the national inventory.

Mattus, C.H.

1998-06-01T23:59:59.000Z

157

Automated Sorting of Transuranic Waste  

SciTech Connect

The HANDSS-55 Transuranic Waste Sorting Module is designed to sort out items found in 55-gallon drums of waste as determined by an operator. Innovative imaging techniques coupled with fast linear motor-based motion systems and a flexible end-effector system allow the operator to remove items from the waste stream by a touch of the finger. When all desired items are removed from the waste stream, the remaining objects are automatically moved to a repackaging port for removal from the glovebox/cell. The Transuranic Waste Sorting Module consists of 1) a high accuracy XYZ Stereo Measurement and Imaging system, 2) a vibrating/tilting sorting table, 3) an XY Deployment System, 4) a ZR Deployment System, 5) several user-selectable end-effectors, 6) a waste bag opening system, 7) control and instrumentation, 8) a noncompliant waste load-out area, and 9) a Human/Machine Interface (HMI). The system is modular in design to accommodate database management tools, additional load-out ports, and other enhancements. Manually sorting the contents of a 55-gallon drum takes about one day per drum. The HANDSS-55 Waste Sorting Module is designed to significantly increase the throughput of this sorting process by automating those functions that are strenuous and tiresome for an operator to perform. The Waste Sorting Module uses the inherent ability of an operator to identify the items that need to be segregated from the waste stream and then, under computer control, picks that item out of the waste and deposits it in the appropriate location. The operator identifies the object by locating the visual image on a large color display and touches the image on the display with his finger. The computer then determines the location of the object, and performing a highspeed image analysis determines its size and orientation, so that a robotic gripper can be deployed to pick it up. Following operator verification by voice or function key, the object is deposited into a specified location.

Shurtliff, Rodney Marvin

2001-03-01T23:59:59.000Z

158

How to deal with laboratory waste Radioactive waste  

E-Print Network (OSTI)

How to deal with laboratory waste Radioactive waste: Any laboratory waste, whether chemical or biological, containing radioactive material, should be disposed as radioactive waste. Radioactive waste should be removed from the laboratory to the departmental waste area, soon after finishing the experiment

Maoz, Shahar

159

Transuranic (TRU) Waste  

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

Defined by the WIPP Land Withdrawal Act as "waste containing more than 100 nanocuries of alpha-emitting transuranic isotopes per gram of waste with half-lives greater than 20 years, except for (A)...

160

Transuranic Waste Screener  

The TRU waste screener (TRU-WS) is a multifunctional system for the rapid screening of transuranic material for criticality safety or screening for TRU content in open trays or waste containers.

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


161

Pioneering Nuclear Waste Disposal  

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

Department of Energy (DOE) is closing the circle on the generation, management, and disposal of transuranic waste. But the WIPP story is not just about radioactive waste. It is...

162

Immobilization of Nuclear Wastes  

Science Conference Proceedings (OSTI)

Oct 20, 2010 ... Glassy and Glass Composite Nuclear Wasteforms: Michael Ojovan1; Bill Lee2; ... wastes which should be solidified for safe storage and disposal. ... has been vitrifying the Department of Energy's High Level Waste (HLW) at ...

163

Pet Waste Management  

E-Print Network (OSTI)

About 1 million pounds of dog waste is deposited daily in North Texas alone. That's why proper disposal of pet waste can make a big difference in the environment. 5 photos, 2 pages

Mechell, Justin; Lesikar, Bruce J.

2008-08-28T23:59:59.000Z

164

The wild wild waste: e-waste  

Science Conference Proceedings (OSTI)

E-Waste is a popular, informal name for discarded electronic products such as computers, VCRs, cameras, which have reached the end of their "useful life". Discarded electronic products contain a stew of toxic metals and chemicals such as lead, mercury, ... Keywords: donate, e-waste, ecology, efficiency, environment, green computing, hazardous material, re-use, recycle, reduce, thin-client, upgrade, virtualization

Scott E. Hanselman; Mahmoud Pegah

2007-10-01T23:59:59.000Z

165

Waste canister for storage of nuclear wastes  

DOE Patents (OSTI)

A waste canister for storage of nuclear wastes in the form of a solidified glass includes fins supported from the center with the tips of the fins spaced away from the wall to conduct heat away from the center without producing unacceptable hot spots in the canister wall.

Duffy, James B. (Fullerton, CA)

1977-01-01T23:59:59.000Z

166

Mixed Waste Treatment Study  

Science Conference Proceedings (OSTI)

As part of an ongoing integrated mixed waste program, EPRI has documented nuclear utility industry experience in the on-site treatment of mixed waste. This report reviews all available exclusions/exceptions to EPA permitting requirements for environmentally responsible on-site management of mixed waste. Included is a description of emerging mixed waste treatment technologies along with a detailed evaluation of off-site treatment/disposal facilities.

1996-01-31T23:59:59.000Z

167

Glassy slags as novel waste forms for remediating mixed wastes with high metal contents  

SciTech Connect

Argonne National Laboratory (ANL) is developing a glassy slag final waste form for the remediation of low-level radioactive and mixed wastes with high metal contents. This waste form is composed of various crystalline and metal oxide phases embedded in a silicate glass phase. This work indicates that glassy slag shows promise as final waste form because (1) it has similar or better chemical durability than high-level nuclear waste (HLW) glasses, (2) it can incorporate large amounts of metal wastes, (3) it can incorporate waste streams having low contents of flux components (boron and alkalis), (4) it has less stringent processing requirements (e.g., viscosity and electric conductivity) than glass waste forms, (5) its production can require little or no purchased additives, which can result in greater reduction in waste volume and overall treatment costs. By using glassy slag waste forms, minimum additive waste stabilization approach can be applied to a much wider range of waste streams than those amenable only to glass waste forms.

Feng, X.; Wronkiewicz, D.J.; Bates, J.K.; Brown, N.R.; Buck, E.C.; Gong, M.; Ebert, W.L.

1994-03-01T23:59:59.000Z

168

Waste Management and WasteWaste Management and Waste--toto--EnergyEnergy Status in SingaporeStatus in Singapore  

E-Print Network (OSTI)

Waste Management and WasteWaste Management and Waste--toto--EnergyEnergy Status in Singapore #12;Singapore's Waste Management · In 2003, 6877 tonnes/day (2.51 M tonnes/year) of MSW collected plants · 8% (non-incinerable waste) and incineration ash goes to the offshore Semakau Landfill · To reach

Columbia University

169

Reducing waste, Photoby stcvcchan  

E-Print Network (OSTI)

I ' I I t Reducing waste, Photoby stcvcchan AMs President Mike Lee (left to right), Point Grey M U recycling given high priority on campus By GAVIN WILSON UBC is taking stepsto reduce waste and encourageGellatly,Vice-President,Administration and Finance,to develop and recommend university policies on waste recycling. Another task force has submitted

Farrell, Anthony P.

170

Hazardous Waste Management Training  

E-Print Network (OSTI)

Hazardous Waste Management Training Persons (including faculty, staff and students) working be thoroughly familiar with waste handling and emergency procedures ap- plicable to their job responsibilities before handling hazardous waste. Departments are re- quired to keep records of training for as long

Dai, Pengcheng

171

Waste disposal package  

DOE Patents (OSTI)

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

Smith, M.J.

1985-06-19T23:59:59.000Z

172

Waste acceptance criteria for closure generated waste  

Science Conference Proceedings (OSTI)

The PORTS Facility has been operating since 1954. The PORTS Facility is used to enrich uranium for nuclear navy applications and commercial nuclear reactors. The PORTS process uses molecular diffusion techniques to separate the U-235 isotope from the U-238 isotope. The PORTS Facility consists of a complex cascade of compressors and converters through which gaseous uranium hexafluoride feed is processed. The feed contains approximately 0.7 percent U-235 by weight while products contain from 4 to 97 percent U-235 by weight, depending on the final application. In general, the majority of the closure wastes generated at PORTS consists of personal protective equipment (PPE), rags, soils, decontamination solutions, and construction related debris. These hazardous wastes will be predominately characterized on the basis of process knowledge. PORTS assumes its conservative waste characterizations that are based on process knowledge are correct unless and until further investigation and/or analysis proves the constituents are not present or are present at concentrations below characteristic regulatory thresholds. Waste Acceptance Criteria for wastes generated by the closure of active and inactive RCRA facilities at PORTS has been developed. The criteria presented in this document govern the activities that are performed during the closure and subsequent generation of waste and relocation from the closure locations to the storage unit. These criteria are intended to ensure the proper handling, classification, processing, and storage of wastes in order to prevent hazardous waste release that may pose a threat to human health or the environment. Any wastes currently stored at each of the facilities that are to be closed will be transferred to the X-326 or X-7725 Storage Units. The waste transfers will be accomplished in accordance with the Container Transfer Plan.

Not Available

1992-05-01T23:59:59.000Z

173

Draft Title 40 CFR 191 compliance certification application for the Waste Isolation Pilot Plant. Volume 3: Appendix BIR Volume 1  

Science Conference Proceedings (OSTI)

The Waste Isolation Pilot Plant (WIPP) Transuranic Waste Baseline Inventory Report (WTWBIR) establishes a methodology for grouping wastes of similar physical and chemical properties, from across the US Department of Energy (DOE) transuranic (TRU) waste system, into a series of ``waste profiles`` that can be used as the basis for waste form discussions with regulatory agencies. The majority of this document reports TRU waste inventories of DOE defense sites. An appendix is included which provides estimates of commercial TRU waste from the West Valley Demonstration Project. The WIPP baseline inventory is estimated using waste streams identified by the DOE TRU waste generator/storage sites, supplemented by information from the Mixed Waste Inventory Report (MWIR) and the 1994 Integrated Data Base (IDB). The sites provided and/or authorized all information in the Waste Stream Profiles except the EPA (hazardous waste) codes for the mixed inventories. These codes were taken from the MWIR (if a WTWBIR mixed waste stream was not in MWIR, the sites were consulted). The IDB was used to generate the WIPP radionuclide inventory. Each waste stream is defined in a waste stream profile and has been assigned a waste matrix code (WMC) by the DOE TRU waste generator/storage site. Waste stream profiles with WMCs that have similar physical and chemical properties can be combined into a waste matrix code group (WMCG), which is then documented in a site-specific waste profile for each TRU waste generator/storage site that contains waste streams in that particular WMCG.

NONE

1995-03-31T23:59:59.000Z

174

Controlled catalytic and thermal sequential pyrolysis and hydrolysis of mixed polymer waste streams to sequentially recover monomers or other high value products  

DOE Patents (OSTI)

A process of using fast pyrolysis in a carrier gas to convert a plastic waste feedstream having a mixed polymeric composition in a manner such that pyrolysis of a given polymer to its high value monomeric constituent occurs prior to pyrolysis of other plastic components therein comprising: selecting a first temperature program range to cause pyrolysis of said given polymer to its high value monomeric constituent prior to a temperature range that causes pyrolysis of other plastic components; selecting a catalyst and support for treating said feed streams with said catalyst to effect acid or base catalyzed reaction pathways to maximize yield or enhance separation of said high value monomeric constituent in said temperature program range; differentially heating said feed stream at a heat rate within the first temperature program range to provide differential pyrolysis for selective recovery of optimum quantities of the high value monomeric constituent prior to pyrolysis of other plastic components; separating the high value monomeric constituents, selecting a second higher temperature range to cause pyrolysis of a different high value monomeric constituent of said plastic waste and differentially heating the feedstream at the higher temperature program range to cause pyrolysis of the different high value monomeric constituent; and separating the different high value monomeric constituent.

Evans, Robert J. (Lakewood, CO); Chum, Helena L. (Arvada, CO)

1994-01-01T23:59:59.000Z

175

Controlled catalytic and thermal sequential pyrolysis and hydrolysis of mixed polymer waste streams to sequentially recover monomers or other high value products  

DOE Patents (OSTI)

A process of using fast pyrolysis in a carrier gas to convert a plastic waste feedstream having a mixed polymeric composition in a manner such that pyrolysis of a given polymer to its high value monomeric constituent occurs prior to pyrolysis of other plastic components therein comprising: selecting a first temperature program range to cause pyrolysis of said given polymer to its high value monomeric constituent prior to a temperature range that causes pyrolysis of other plastic components; selecting a catalyst and support for treating said feed streams with said catalyst to effect acid or base catalyzed reaction pathways to maximize yield or enhance separation of said high value monomeric constituent in said temperature program range; differentially heating said feed stream at a heat rate within the first temperature program range to provide differential pyrolysis for selective recovery of optimum quantities of the high value monomeric constituent prior to pyrolysis of other plastic components; separating the high value monomeric constituents; selecting a second higher temperature range to cause pyrolysis of a different high value monomeric constituent of said plastic waste and differentially heating the feedstream at the higher temperature program range to cause pyrolysis of the different high value monomeric constituent; and separating the different high value monomeric constituent.

Evans, Robert J. (Lakewood, CO); Chum, Helena L. (Arvada, CO)

1993-01-01T23:59:59.000Z

176

Controlled catalytic and thermal sequential pyrolysis and hydrolysis of mixed polymer waste streams to sequentially recover monomers or other high value products  

DOE Patents (OSTI)

A process of using fast pyrolysis in a carrier gas to convert a plastic waste feedstream having a mixed polymeric composition in a manner such that pyrolysis of a given polymer to its high value monomeric constituent occurs prior to pyrolysis of other plastic components therein comprising: selecting a first temperature program range to cause pyrolysis of said given polymer to its high value monomeric constituent prior to a temperature range that causes pyrolysis of other plastic components; selecting a catalyst and support for treating said feed streams with said catalyst to effect acid or base catalyzed reaction pathways to maximize yield or enhance separation of said high value monomeric constituent in said temperature program range; differentially heating said feed stream at a heat rate within the first temperature program range to provide differential pyrolysis for selective recovery of optimum quantities of the high value monomeric constituent prior to pyrolysis of other plastic components; separating the high value monomeric constituents; selecting a second higher temperature range to cause pyrolysis of a different high value monomeric constituent of said plastic waste and differentially heating the feedstream at the higher temperature program range to cause pyrolysis of the different high value monomeric constituent; and separating the different high value monomeric constituent.

Evans, Robert J. (Lakewood, CO); Chum, Helena L. (Arvada, CO)

1994-01-01T23:59:59.000Z

177

Controlled catalytic and thermal sequential pyrolysis and hydrolysis of mixed polymer waste streams to sequentially recover monomers or other high value products  

DOE Patents (OSTI)

A process is described for using fast pyrolysis in a carrier gas to convert a plastic waste feedstream having a mixed polymeric composition in a manner such that pyrolysis of a given polymer to its high value monomeric constituent occurs prior to pyrolysis of other plastic components therein comprising: selecting a first temperature program range to cause pyrolysis of said given polymer to its high value monomeric constituent prior to a temperature range that causes pyrolysis of other plastic components; selecting a catalyst and support for treating said feed streams with said catalyst to effect acid or base catalyzed reaction pathways to maximize yield or enhance separation of said high value monomeric constituent in said temperature program range; differentially heating said feed stream at a heat rate within the first temperature program range to provide differential pyrolysis for selective recovery of optimum quantities of the high value monomeric constituent prior to pyrolysis of other plastic components; separating the high value monomeric constituents, selecting a second higher temperature range to cause pyrolysis of a different high value monomeric constituent of said plastic waste and differentially heating the feedstream at the higher temperature program range to cause pyrolysis of the different high value monomeric constituent; and separating the different high value monomeric constituent. 87 figures.

Evans, R.J.; Chum, H.L.

1994-04-05T23:59:59.000Z

178

Controlled catalytic and thermal sequential pyrolysis and hydrolysis of mixed polymer waste streams to sequentially recover monomers or other high value products  

DOE Patents (OSTI)

A process of using fast pyrolysis in a carrier gas to convert a plastic waste feedstream having a mixed polymeric composition in a manner such that pyrolysis of a given polymer to its high value monomeric constituent occurs prior to pyrolysis of other plastic components therein comprising: selecting a first temperature program range to cause pyrolysis of said given polymer to its high value monomeric constituent prior to a temperature range that causes pyrolysis of other plastic components; selecting a catalyst and support for treating said feed streams with said catalyst to effect acid or base catalyzed reaction pathways to maximize yield or enhance separation of said high value monomeric constituent in said temperature program range; differentially heating said feed stream at a heat rate within the first temperature program range to provide differential pyrolysis for selective recovery of optimum quantities of the high value monomeric constituent prior to pyrolysis of other plastic components; separating the high value monomeric constituents; selecting a second higher temperature range to cause pyrolysis of a different high value monomeric constituent of said plastic waste and differentially heating the feedstream at the higher temperature program range to cause pyrolysis of the different high value monomeric constituent; and separating the different high value monomeric constituent. 83 figs.

Evans, R.J.; Chum, H.L.

1994-10-25T23:59:59.000Z

179

Waste Disposal Matrix Type of Chemical University-related Waste Personal Waste  

E-Print Network (OSTI)

Waste Disposal Matrix Type of Chemical University-related Waste Personal Waste Batteries, used or unwanted including lithium, alkaline, lead ­ acid or lithium aluminum hydride Chemical Waste Check Disposal of Toxics website for disposal options or Take to Bookstore Biological Waste Biological Waste Residential

Zaferatos, Nicholas C.

180

Radioactive Waste Management Basis  

SciTech Connect

The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Perkins, B K

2009-06-03T23:59:59.000Z

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

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

182

ASSEMBLAGES ON WASTE ROCK  

E-Print Network (OSTI)

Abstract: Natural regeneration on waste rock was investigated at the old Wangaloa coal mine, south-east Otago. A 450-m long waste rock stack had been created 40–50 years ago, and has had little anthropogenic intervention since. The stack is made up of a gradient of three main waste rock types, defined as ‘silt-rich’, ‘mixed’, and ‘quartz-rich’, which reflect different proportions of loess siltstone and quartz gravel conglomerate. Plant species assemblages were quantified in four 5-m 2 quadrats in each waste rock type. Invertebrates were heat extracted from substrate cores (7 cm diameter; depth 5 cm) collected from quadrats over an eight-week period in spring 2003. Ordination analysis showed statistically distinct plant and invertebrate assemblages had arisen on each waste rock type. Revegetation patterns were dominated by native, woody individuals on all waste rock types, particularly manuka (Leptospermum scoparium) and kanuka (Kunzea ericoides). Plant cover on ‘silt-rich ’ waste rock was four-fold that on ‘quartz-rich ’ waste rock. Total numbers of invertebrates were highest on ‘quartz-rich’ waste rock, but richness greatest on ‘silt-rich ’ waste rock. Collembola dominated the fauna but their numbers were proportionally greatest in poorly vegetated areas. Further work is required to explain the absence of plants and invertebrates from local areas of waste rock. ___________________________________________________________________________________________________________________________________

C. G. Rufaut; S. Hammit; D. Craw; S. G. Clearwater

2006-01-01T23:59:59.000Z

183

Mixed waste: Proceedings  

SciTech Connect

This volume contains the peer-reviewed and edited versions of papers submitted for presentation a the Second International Mixed Waste Symposium. Following the tradition of the First International Mixed Waste Symposium, these proceedings were prepared in advance of the meeting for distribution to participants. The symposium was organized by the Mixed Waste Committee of the American Society of Mechanical Engineers. The topics discussed at the symposium include: stabilization technologies, alternative treatment technologies, regulatory issues, vitrification technologies, characterization of wastes, thermal technologies, laboratory and analytical issues, waste storage and disposal, organic treatment technologies, waste minimization, packaging and transportation, treatment of mercury contaminated wastes and bioprocessing, and environmental restoration. Individual abstracts are catalogued separately for the data base.

Moghissi, A.A.; Blauvelt, R.K.; Benda, G.A.; Rothermich, N.E. [eds.] [Temple Univ., Philadelphia, PA (United States). Dept. of Environmental Safety and Health

1993-12-31T23:59:59.000Z

184

Hanford Site solid waste acceptance criteria  

SciTech Connect

Order 5820.2A requires that each treatment, storage, and/or disposal facility (referred to in this document as TSD unit) that manages low-level or transuranic waste (including mixed waste and TSCA PCB waste) maintain waste acceptance criteria. These criteria must address the various requirements to operate the TSD unit in compliance with applicable safety and environmental requirements. This document sets forth the baseline criteria for acceptance of radioactive waste at TSD units operated by WMH. The criteria for each TSD unit have been established to ensure that waste accepted can be managed in a manner that is within the operating requirements of the unit, including environmental regulations, DOE Orders, permits, technical safety requirements, waste analysis plans, performance assessments, and other applicable requirements. Acceptance criteria apply to the following TSD units: the Low-Level Burial Grounds (LLBG) including both the nonregulated portions of the LLBG and trenches 31 and 34 of the 218-W-5 Burial Ground for mixed waste disposal; Central Waste Complex (CWC); Waste Receiving and Processing Facility (WRAP); and T Plant Complex. Waste from all generators, both from the Hanford Site and from offsite facilities, must comply with these criteria. Exceptions can be granted as provided in Section 1.6. Specific waste streams could have additional requirements based on the 1901 identified TSD pathway. These requirements are communicated in the Waste Specification Records (WSRds). The Hanford Site manages nonradioactive waste through direct shipments to offsite contractors. The waste acceptance requirements of the offsite TSD facility must be met for these nonradioactive wastes. This document does not address the acceptance requirements of these offsite facilities.

Ellefson, M.D.

1998-07-01T23:59:59.000Z

185

SALTSTONE VAULT CLASSIFICATION SAMPLES MODULAR CAUSTIC SIDE SOLVENT EXTRACTION UNIT/ACTINIDE REMOVAL PROCESS WASTE STREAM APRIL 2011  

Science Conference Proceedings (OSTI)

Savannah River National Laboratory (SRNL) was asked to prepare saltstone from samples of Tank 50H obtained by SRNL on April 5, 2011 (Tank 50H sampling occurred on April 4, 2011) during 2QCY11 to determine the non-hazardous nature of the grout and for additional vault classification analyses. The samples were cured and shipped to Babcock & Wilcox Technical Services Group-Radioisotope and Analytical Chemistry Laboratory (B&W TSG-RACL) to perform the Toxic Characteristic Leaching Procedure (TCLP) and subsequent extract analysis on saltstone samples for the analytes required for the quarterly analysis saltstone sample. In addition to the eight toxic metals - arsenic, barium, cadmium, chromium, mercury, lead, selenium and silver - analytes included the underlying hazardous constituents (UHC) antimony, beryllium, nickel, and thallium which could not be eliminated from analysis by process knowledge. Additional inorganic species determined by B&W TSG-RACL include aluminum, boron, chloride, cobalt, copper, fluoride, iron, lithium, manganese, molybdenum, nitrate/nitrite as Nitrogen, strontium, sulfate, uranium, and zinc and the following radionuclides: gross alpha, gross beta/gamma, 3H, 60Co, 90Sr, 99Tc, 106Ru, 106Rh, 125Sb, 137Cs, 137mBa, 154Eu, 238Pu, 239/240Pu, 241Pu, 241Am, 242Cm, and 243/244Cm. B&W TSG-RACL provided subsamples to GEL Laboratories, LLC for analysis for the VOCs benzene, toluene, and 1-butanol. GEL also determines phenol (total) and the following radionuclides: 147Pm, 226Ra and 228Ra. Preparation of the 2QCY11 saltstone samples for the quarterly analysis and for vault classification purposes and the subsequent TCLP analyses of these samples showed that: (1) The saltstone waste form disposed of in the Saltstone Disposal Facility in 2QCY11 was not characteristically hazardous for toxicity. (2) The concentrations of the eight RCRA metals and UHCs identified as possible in the saltstone waste form were present at levels below the UTS. (3) Most of the inorganic species measured in the leachate do not exceed the MCL, SMCL or TW limits. (4) The inorganic waste species that exceeded the MCL by more than a factor of 10 were nitrate, nitrite and the sum of nitrate and nitrite. (5) Analyses met all quality assurance specifications of US EPA SW-846. (6) The organic species (benzene, toluene, 1-butanol, phenol) were either not detected or were less than reportable for the vault classification samples. (7) The gross alpha and radium isotopes could not be determined to the MCL because of the elevated background which raised the detection limits. (8) Most of the beta/gamma activity was from 137Cs and its daughter 137mBa. (9) The concentration of 137Cs and 90Sr were present in the leachate at concentrations 1/40th and 1/8th respectively than in the 2003 vault classification samples. The saltstone waste form placed in the Saltstone Disposal Facility in 2QCY11 met the SCHWMR R.61-79.261.24(b) RCRA metals requirements for a nonhazardous waste form. The TCLP leachate concentrations for nitrate, nitrite and the sum of nitrate and nitrite were greater than 10x the MCLs in SCDHEC Regulations R.61-107.19, Part I A, which confirms the Saltstone Disposal Facility classification as a Class 3 Landfill. The saltstone waste form placed in the Saltstone Disposal Facility in 2QCY11 met the R.61-79.268.48(a) non wastewater treatment standards.

Eibling, R.

2011-09-28T23:59:59.000Z

186

Minimum Additive Waste Stabilization (MAWS). Technology summary  

Science Conference Proceedings (OSTI)

In the Minimum Additive Waste Stabilization(MAWS) concept, actual waste streams are utilized as additive resources for vitrification, which may contain the basic components (glass formers and fluxes) for making a suitable glass or glassy slag. If too much glass former is present, then the melt viscosity or temperature will be too high for processing; while if there is too much flux, then the durability may suffer. Therefore, there are optimum combinations of these two important classes of constituents depending on the criteria required. The challenge is to combine these resources in such a way that minimizes the use of non-waste additives yet yields a processable and durable final waste form for disposal. The benefit to this approach is that the volume of the final waste form is minimized (waste loading maximized) since little or no additives are used and vitrification itself results in volume reduction through evaporation of water, combustion of organics, and compaction of the solids into a non-porous glass. This implies a significant reduction in disposal costs due to volume reduction alone, and minimizes future risks/costs due to the long term durability and leach resistance of glass. This is accomplished by using integrated systems that are both cost-effective and produce an environmentally sound waste form for disposal. individual component technologies may include: vitrification; thermal destruction; soil washing; gas scrubbing/filtration; and, ion-exchange wastewater treatment. The particular combination of technologies will depend on the waste streams to be treated. At the heart of MAWS is vitrification technology, which incorporates all primary and secondary waste streams into a final, long-term, stabilized glass wasteform. The integrated technology approach, and view of waste streams as resources, is innovative yet practical to cost effectively treat a broad range of DOE mixed and low-level wastes.

Not Available

1994-02-01T23:59:59.000Z

187

Physical and chemical characteristics of candidate wastes for tailored ceramics  

Science Conference Proceedings (OSTI)

Tailored Ceramics offer a potential alternative to glass as an immobilization form for nuclear waste disposal. The form is applicable to the wide variety of existing wastes and may be tailored to suit the diverse environments being considered as disposal sites. Consideration of any waste product form, however, require extensive knowledge of the waste to be incorporated. A varity of waste types are under consideration for incorporation into a Tailored Ceramic form. This report integrates and summarizes chemical and physical characteristics of the candidate wastes. Included here are data on Savannah River Purex Process waste; Hanford bismuth phosphate, uranium recovery, redox, Purex, evaporator and residual liquid wastes; Idaho Falls calcine; Nuclear Fuel Services Purex and Thorex wastes and miscellaneous waste including estimated waste stream compositions produced by possible future commercial fuel reprocessing.

Mitchell, M.E.

1980-12-15T23:59:59.000Z

188

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

189

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

190

Waste Confidence Discussion | Department of Energy  

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

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

191

Integrated Waste Services Association National Solid Wastes Management Association  

E-Print Network (OSTI)

Can Help Meet Our Energy Needs October 5, 2006 - WASHINGTON, DC--A broad coalition of government-244-4700 Evan Von Leer, SWANA 240-494-2252 John Varrasi, ASME 212-591-8158 Don't Waste Waste! Waste-Based Energy and utilization of energy produced from waste, or waste-based energy (WBE). The United States Conference of Mayors

Columbia University

192

Energy from Waste UK Joint Statement on Energy from Waste  

E-Print Network (OSTI)

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

193

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

E-Print Network (OSTI)

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

194

Radioactive Waste: 1. Radioactive waste from your lab is  

E-Print Network (OSTI)

Radioactive Waste: 1. Radioactive waste from your lab is collected by the RSO. 2. Dry radioactive waste must be segregated by isotope. 3. Liquid radioactive waste must be separated by isotope. 4. Liquid scintillation vials must be collected separately. 5. Any "mixed waste" must be cleared with the RSO and labeled

195

Controlled catalytic and thermal sequential pyrolysis and hydrolysis of phenolic resin containing waste streams to sequentially recover monomers and chemicals  

DOE Patents (OSTI)

A process is described for using fast pyrolysis in a carrier gas to convert a waste phenolic resin containing feedstreams in a manner such that pyrolysis of said resins and a given high value monomeric constituent occurs prior to pyrolyses of the resins in other monomeric components therein comprising: selecting a first temperature program range to cause pyrolysis of said resin and a given high value monomeric constituent prior to a temperature range that causes pyrolysis of other monomeric components; selecting, if desired, a catalyst and a support and treating said feedstreams with said catalyst to effect acid or basic catalyzed reaction pathways to maximize yield or enhance separation of said high value monomeric constituent in said first temperature program range to utilize reactive gases such as oxygen and steam in the pyrolysis process to drive the production of specific products; differentially heating said feedstreams at a heat rate within the first temperature program range to provide differential pyrolysis for selective recovery of optimum quantity of said high value monomeric constituent prior to pyrolysis of other monomeric components therein; separating said high value monomeric constituent; selecting a second higher temperature program range to cause pyrolysis of a different high value monomeric constituent of said phenolic resins waste and differentially heating said feedstreams at said higher temperature program range to cause pyrolysis of said different high value monomeric constituent; and separating said different high value monomeric constituent. 11 figs.

Chum, H.L.; Evans, R.J.

1992-08-04T23:59:59.000Z

196

Military Munitions Waste Working Group report  

SciTech Connect

This report presents the findings of the Military Munitions Waste Working Group in its effort to achieve the goals directed under the Federal Advisory Committee to Develop On-Site Innovative Technologies (DOIT Committee) for environmental restoration and waste management. The Military Munitions Waste Working Group identified the following seven areas of concern associated with the ordnance (energetics) waste stream: unexploded ordnance; stockpiled; disposed -- at known locations, i.e., disposal pits; discharged -- impact areas, unknown disposal sites; contaminated media; chemical sureties/weapons; biological weapons; munitions production; depleted uranium; and rocket motor and fuel disposal (open burn/open detonation). Because of time constraints, the Military Munitions Waste Working Group has focused on unexploded ordnance and contaminated media with the understanding that remaining waste streams will be considered as time permits. Contents of this report are as follows: executive summary; introduction; Military Munitions Waste Working Group charter; description of priority waste stream problems; shortcomings of existing approaches, processes and technologies; innovative approaches, processes and technologies, work force planning, training, and education issues relative to technology development and cleanup; criteria used to identify and screen potential demonstration projects; list of potential candidate demonstration projects for the DOIT committee decision/recommendation and appendices.

Not Available

1993-11-30T23:59:59.000Z

197

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

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

Waste Management Tank Waste and Waste Processing Integrated Waste Treatment Facility Fact Sheet Integrated Waste Treatment Facility Fact Sheet Waste Management Nuclear...

198

NDAA Section 3116 Waste Determinations with Related Disposal...  

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

NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments Waste Management Nuclear Materials & Waste Tank Waste and Waste Processing Waste...

199

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

200

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

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

Hanford Site waste treatment/storage/disposal integration  

SciTech Connect

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

MCDONALD, K.M.

1999-02-24T23:59:59.000Z

202

Pioneering Nuclear Waste Disposal  

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

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

203

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

204

Underground waste barrier structure  

DOE Patents (OSTI)

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

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

1988-01-01T23:59:59.000Z

205

Guidelines for mixed waste minimization  

SciTech Connect

Currently, there is no commercial mixed waste disposal available in the United States. Storage and treatment for commercial mixed waste is limited. Host States and compacts region officials are encouraging their mixed waste generators to minimize their mixed wastes because of management limitations. This document provides a guide to mixed waste minimization.

Owens, C.

1992-02-01T23:59:59.000Z

206

Operational Waste Volume Projection  

SciTech Connect

Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement. Assumptions were current as of June. 2000.

STRODE, J.N.

2000-08-28T23:59:59.000Z

207

Turning Waste Heat into Power: Ener-G-Rotors and the Entrepreneurial...  

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

(below 400 degrees F) into electricity. The waste heat stream is diverted through a "hot heat exchanger" inside the system. A cooling stream is simultaneously diverted through the...

208

Customer service model for waste tracking at Los Alamos National Laboratory  

SciTech Connect

The goal is to transition from five legacy database systems that have reached end-of-life to a single inventory system that supports workflow, data, and reporting for all waste streams. Plutonium Processing Facility (TA-55) Waste Team provides a high quality system that insures safe, efficient and compliant management of all radioactive and hazardous wastes generated, including waste characterization and repackaging of Transuranic Waste (TRU) and TRU mixed waste for shipment to the Waste Isolation Pilot Plant (WIPP).

Dorries, Alison M [Los Alamos National Laboratory

2011-02-02T23:59:59.000Z

209

Norcal Waste Systems, Inc.  

SciTech Connect

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

Not Available

2002-12-01T23:59:59.000Z

210

Waste Confidence Discussion  

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

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

211

Solid Waste Permits (Louisiana)  

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

The Louisiana Department of Environmental Quality administers the rules and regulations governing the storage, collection, processing, recovery, and reuse of solid waste protect the air,...

212

Nuclear Waste Management  

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

Waste Management's Yucca Mountain Project and the Office of Nuclear Energy's Advanced Fuel Cycle Initiative (AFCI) and Global Nuclear Energy Partnership (GNEP) programs. Efforts...

213

Vitrification of waste  

DOE Patents (OSTI)

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

Wicks, G.G.

1999-04-06T23:59:59.000Z

214

The Power of Waste.  

E-Print Network (OSTI)

?? Abstract It is estimated that up to 2 percent of the population in Third World countries survives on waste in one way or another.… (more)

Frykman, Carina

2006-01-01T23:59:59.000Z

215

Making waste public.  

E-Print Network (OSTI)

??This thesis questions the boundaries that define waste as a public or private dilemma, investigating these boundaries as productive sites for the imagination of social… (more)

Gambetta, Curt

2009-01-01T23:59:59.000Z

216

Vitrification of waste  

DOE Patents (OSTI)

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

Wicks, George G. (Aiken, SC)

1999-01-01T23:59:59.000Z

217

Make love not waste.  

E-Print Network (OSTI)

?? The purpose of this thesis was to investigate a waste management project and its public awareness components, in the Korca region, Albania. We wanted… (more)

Carlsson Engström, Christina

2008-01-01T23:59:59.000Z

218

Making Waste Public.  

E-Print Network (OSTI)

??This thesis questions the boundaries that define waste as a public or private dilemma, investigating these boundaries as productive sites for the imagination of social… (more)

Gambetta, Curt

2009-01-01T23:59:59.000Z

219

WEB RESOURCE: Radioactive Waste  

Science Conference Proceedings (OSTI)

May 8, 2007 ... This resource offers a a very broad explanation of how the Belgian Agency for Management of Radioactive Waste and Enriched Fissile Material ...

220

Integrated waste management.  

E-Print Network (OSTI)

??Integrated waste management is considered from a systems’ approach, with a particular emphasis on advancing sustainability. The focus of the thesis is to examine the… (more)

Seadon, Jeffrey Keith

2010-01-01T23:59:59.000Z

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


221

Waste Clean Up 5  

Science Conference Proceedings (OSTI)

... deployment and clean-up activities of robot arms into a nuclear contaminated pit at the opening of waste storage tank C-106 at Hanford, Washington ...

2011-08-30T23:59:59.000Z

222

DOE mixed waste treatment capacity analysis  

SciTech Connect

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

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

1994-06-01T23:59:59.000Z

223

Stabilization and disposal of Argonne-West low-level mixed wastes in ceramicrete waste forms.  

SciTech Connect

The technology of room-temperature-setting phosphate ceramics or Ceramicrete{trademark} technology, developed at Argonne National Laboratory (ANL)-East is being used to treat and dispose of low-level mixed wastes through the Department of Energy complex. During the past year, Ceramicrete{trademark} technology was implemented for field application at ANL-West. Debris wastes were treated and stabilized: (a) Hg-contaminated low-level radioactive crushed light bulbs and (b) low-level radioactive Pb-lined gloves (part of the MWIR {number_sign} AW-W002 waste stream). In addition to hazardous metals, these wastes are contaminated with low-level fission products. Initially, bench-scale waste forms with simulated and actual waste streams were fabricated by acid-base reactions between mixtures of magnesium oxide powders and an acid phosphate solution, and the wastes. Size reduction of Pb-lined plastic glove waste was accomplished by cryofractionation. The Ceramicrete{trademark} process produces dense, hard ceramic waste forms. Toxicity Characteristic Leaching Procedure (TCLP) results showed excellent stabilization of both Hg and Pb in the waste forms. The principal advantage of this technology is that immobilization of contaminants is the result of both chemical stabilization and subsequent microencapsulation of the reaction products. Based on bench-scale studies, Ceramicrete{trademark} technology has been implemented in the fabrication of 5-gal waste forms at ANL-West. Approximately 35 kg of real waste has been treated. The TCLP is being conducted on the samples from the 5-gal waste forms. It is expected that because the waste forms pass the limits set by the EPAs Universal Treatment Standard, they will be sent to a radioactive-waste disposal facility.

Barber, D. B.; Singh, D.; Strain, R. V.; Tlustochowicz, M.; Wagh, A. S.

1998-02-17T23:59:59.000Z

224

Pulling History from the Waste Stream: Identification and Collection of Manhattan Project and Cold War Era Artifacts on the Hanford Site  

SciTech Connect

One man?s trash is another man?s treasure. Not everything called ?waste? is meant for the refuse pile. The mission of the Curation Program is at direct odds with the remediation objectives of the Hanford Site. While others are busily tearing down and burying the Site?s physical structures and their associated contents, the Curation Program seeks to preserve the tangible elements of the Site?s history from these structures for future generations before they flow into the waste stream. Under the provisions of a Programmatic Agreement, Cultural Resources staff initiated a project to identify and collect artifacts and archives that have historic or interpretive value in documenting the role of the Hanford Site throughout the Manhattan Project and Cold War Era. The genesis of Hanford?s modern day Curation Program, its evolution over nearly two decades, issues encountered, and lessons learned along the way ? particularly the importance of upper management advocacy, when and how identification efforts should be accomplished, the challenges of working within a radiological setting, and the importance of ?first hand? information ? are presented.

Marceau, Thomas E.; Watson, Thomas L.

2013-11-13T23:59:59.000Z

225

Comparative evaluation of DHDECMP (dihexyl-N,N-diethylcarbamoyl-methylphosphonate) and CMPO (octylphenyl-N,N,-diisobutylcarbamoylmethylphosphine oxide) as extractants for recovering actinides from nitric acid waste streams  

SciTech Connect

Certain neutral, bifunctional organophosphorous compounds are of special value to the nuclear industry. Dihexyl-N,N-diethylcarbomoylmethylphosphonate (DHDECMP) and octylphenyl-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) are highly selective extractants for removing actinide and lanthanide elements from nitric acid. We obtained these two extractants from newly available commercial sources and evaluated them for recovering Am(III), Pu(IV), and U(VI) from nitric acid waste streams of plutonium processing operations. Variables included the extractant (DHSECMP or CMPO), extractant/tributylphosphate ratio, diluent, nitrate concentration, nitrate salt/nitric acid ratio, fluoride concentration, and contact time. Based on these experimental data, we selected DHDECMP as the perferred extractant for this application. 18 refs., 30 figs.

Marsh, S.F.; Yarbro, S.L.

1988-02-01T23:59:59.000Z

226

Hazardous chemical waste abatement, reduction, reuse, and recycle  

Science Conference Proceedings (OSTI)

The aim of waste abatement, reduction, reuse, and recycle processes is to minimize the need for waste treatment, storage, and disposal facilities. In many cases, this can be accomplished in a cost-effective manner since the economics of recovery and reuse are often more favorable than the disposal of the waste and purchase of new raw material. Consequently, there is increasing interest in technologies that produce less waste and provide for the recovery of resources from some waste streams. This paper discusses some of these technologies. Waste abatement (the substitution of a new low-waste process or material to reduce waste quantities) is discussed, and four examples are given. Waste reduction or modification (decreasing wastes by housekeeping practices, concentration methods, or simple in-plant treatment) technologies are presented with a focus on metals recovery and waste volume reduction. Waste reuse (direct reuse of a waste as a raw material, either as is, or with minor modification) examples discussed include solvent reuse and the utilization of fly ash in structural materials. Waste recycle and recovery (the recovery of resources from waste streams through the application of reprocessing technologies) is discussed using examples of solvent recovery and drum reclamation.

Rodgers, B.R.

1985-01-01T23:59:59.000Z

227

Waste Isolation Pilot Plant (WIPP) Waste Isolation Pilot Plant...  

National Nuclear Security Administration (NNSA)

dispose of transuranic radioactive waste, or TRU waste, left over from the production of nuclear weapons. After more than 20 years of scientific study, public input, and...

228

Virginia Waste Management Act (Virginia)  

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

Solid waste and hazardous waste are regulated under a number of programs at the Department of Environmental Quality. These programs are designed to encourage the reuse and recycling of solid waste...

229

Solid Waste Act (New Mexico)  

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

The main purpose of the Solid Waste Act is to authorize and direct the establishment of a comprehensive solid waste management program. The act states details about specific waste management...

230

Solid Waste Disposal Act (Texas)  

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

The Texas Commission on Environmental Quality is responsible for the regulation and management of municipal solid waste and hazardous waste. A fee is applied to all solid waste disposed in the...

231

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...

232

Chapter 19 - Nuclear Waste Fund  

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

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

233

Animal Waste Technology Fund (Maryland)  

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

A bill passed in 2012 transferred responsibility for animal waste management technology projects to the Maryland Department of Agriculture. The Department will maintain the Animal Waste Technology...

234

Drilling Waste Management Technology Descriptions  

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

skip navigation Drilling Waste Management Information System: The information resource for better management of drilling wastes DWM Logo Search Search you are in this section...

235

Municipal Waste Combustion (New Mexico)  

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

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

236

Hazardous Waste Management (New Mexico)  

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

The New Mexico Environment Department's Hazardous Waste Bureau is responsible for the management of hazardous waste in the state. The Bureau enforces the rules established by the Environmental...

237

Solid waste management of Jakarta.  

E-Print Network (OSTI)

?? Solid waste management has been one of the critical issues in Jakarta, Indonesia.With enormous amounts of generated waste per day and limited supportinginfrastructure, the… (more)

Trisyanti, Dini

2004-01-01T23:59:59.000Z

238

Treatment of Waste Soils / Solids  

Science Conference Proceedings (OSTI)

About the 1996 International Symposium on Extraction and Processing for the Treatment and Minimization of Wastes: Treatment of Waste Soils / Solids ...

239

Mixed Waste Management Guidelines  

Science Conference Proceedings (OSTI)

The management of mixed waste presents serious challenges to nuclear utilities. Regulatory and practical predicaments make compliance with the letter of all applicable regulations extremely difficult. Utility experts developed these guidelines to identify opportunities for improving work practices and regulatory compliance while minimizing any potential adverse impacts of mixed waste management.

1994-12-31T23:59:59.000Z

240

Radioactive waste storage issues  

SciTech Connect

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

Kunz, D.E.

1994-08-15T23:59:59.000Z

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

Radioactive waste disposal package  

DOE Patents (OSTI)

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

Lampe, Robert F. (Bethel Park, PA)

1986-01-01T23:59:59.000Z

242

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

243

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

SciTech Connect

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

1995-02-01T23:59:59.000Z

244

Pioneering Nuclear Waste Disposal  

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

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

245

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%)

246

HLW Glass Waste Loadings  

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

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

247

AVLIS production plant waste management plan  

Science Conference Proceedings (OSTI)

Following the executive summary, this document contains the following: (1) waste management facilities design objectives; (2) AVLIS production plant wastes; (3) waste management design criteria; (4) waste management plan description; and (5) waste management plan implementation. 17 figures, 18 tables.

Not Available

1984-11-15T23:59:59.000Z

248

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

SciTech Connect

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

NSTec Environmental Restoration

2012-02-16T23:59:59.000Z

249

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

SciTech Connect

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

,

2013-02-21T23:59:59.000Z

250

Radiological, physical, and chemical characterization of additional alpha contaminated and mixed low-level waste for treatment at the advanced mixed waste treatment project  

SciTech Connect

This document provides physical, chemical, and radiological descriptive information for a portion of mixed waste that is potentially available for private sector treatment. The format and contents are designed to provide treatment vendors with preliminary information on the characteristics and properties for additional candidate portions of the Idaho National Engineering Laboratory (INEL) and offsite mixed wastes not covered in the two previous characterization reports for the INEL-stored low-level alpha-contaminated and transuranic wastes. This report defines the waste, provides background information, briefly reviews the requirements of the Federal Facility Compliance Act (P.L. 102-386), and relates the Site Treatment Plans developed under the Federal Facility Compliance Act to the waste streams described herein. Each waste is summarized in a Waste Profile Sheet with text, charts, and tables of waste descriptive information for a particular waste stream. A discussion of the availability and uncertainty of data for these waste streams precedes the characterization descriptions.

Hutchinson, D.P.

1995-07-01T23:59:59.000Z

251

ICDF Complex Waste Profile and Verification Sample Guidance  

Science Conference Proceedings (OSTI)

This guidance document will assist waste generators who characterize waste streams destined for disposal at the Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) Complex. The purpose of this document is to develop a conservative but appropriate way to (1) characterize waste for entry into the ICDF; (2) ensure compliance with the waste acceptance criteria; and (3) facilitate disposal at the ICDF landfill or evaporation pond. In addition, this document will establish the waste verification process used by ICDF personnel to ensure that untreated waste meets applicable ICDF acceptance limits

W. M. Heileson

2006-10-01T23:59:59.000Z

252

Waste Class B/C Reduction Guide, Revision 1  

Science Conference Proceedings (OSTI)

Low level waste (LLW) Class B/C wet waste, including filter and ion exchange media, is one of the most expensive radioactive wastes routinely generated by U.S. commercial reactors8212up to a factor of 10 higher than lower activity waste streams. This report is a continuation of the EPRI initiative to evaluate techniques and technologies that reduce the generation and packaged volume of Class B/C wastes. In addition to reducing Class B/C waste generation, several techniques described in this study also su...

2011-11-23T23:59:59.000Z

253

The Mixed Waste Management Facility. Preliminary design review  

Science Conference Proceedings (OSTI)

This document presents information about the Mixed Waste Management Facility. Topics discussed include: cost and schedule baseline for the completion of the project; evaluation of alternative options; transportation of radioactive wastes to the facility; capital risk associated with incineration; radioactive waste processing; scaling of the pilot-scale system; waste streams to be processed; molten salt oxidation; feed preparation; initial operation to demonstrate selected technologies; floorplans; baseline revisions; preliminary design baseline; cost reduction; and project mission and milestones.

NONE

1995-12-31T23:59:59.000Z

254

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

255

Waste Management & Research290 Waste Manage Res 2002: 20: 290301  

E-Print Network (OSTI)

Waste Management & Research290 Waste Manage Res 2002: 20: 290­301 Printed in UK ­ all rights reserved Copyright © ISWA 2002 Waste Management & Research ISSN 0734­242X Introduction Chromated copper of sorting technologies for CCA treated wood waste Monika Blassino Helena Solo-Gabriele University of Miami

Florida, University of

256

L/O/G/OL/O/G/O Waste Waste  

E-Print Network (OSTI)

L/O/G/OL/O/G/O #12;· Waste Waste · Value () · · Flow #12;Genchi GenbutsuGenchi Genbutsu Top management should participate in regular "Ground Zero" walks CQI CQI RCA #12; waste/ value waste/ value · Eliminate · Re-arrange · Re-structure · Simplify · Combine · IT #12

Laksanacharoen, Sathaporn

257

WASTE SEPARATION-DOES IT INFLUENCE MUNICIPAL WASTE COMBUSTOR EMISSIONS?  

E-Print Network (OSTI)

WASTE SEPARATION- DOES IT INFLUENCE MUNICIPAL WASTE COMBUSTOR EMISSIONS? A. John Chandler A a commendable job in proving that trace emissions from a modem waste to energy plant have little to do with the trace compounds in individual components of municipal solid waste. Ogden, the leader in designing

Columbia University

258

FROM WASTE TO WORTH: THE ROLE OF WASTE DIVERSION IN  

E-Print Network (OSTI)

FROM WASTE TO WORTH: THE ROLE OF WASTE DIVERSION IN THE GREEN ECONOMY Submission to the Ministry of the Environment Regarding the Minister's Report on the Waste Diversion Act 2002 Review Submitted by: Submitted to of the Environment 10 Rambert Crescent Integrated Environmental Policy Division Toronto, Ontario M6S 1E6 Waste

Columbia University

259

Treatment of Radioactive Reactive Mixed Waste  

Science Conference Proceedings (OSTI)

PacificEcoSolutions, Inc. (PEcoS) has installed a plasma gasification system that was recently modified and used to destroy a trimethyl-aluminum mixed waste stream from Los Alamos National Laboratory (LANL.) The unique challenge in handling reactive wastes like trimethyl-aluminum is their propensity to flame instantly on contact with air and to react violently with water. To safely address this issue, PacificEcoSolutions has developed a new feed system to ensure the safe containment of these radioactive reactive wastes during transfer to the gasification unit. The plasma gasification system safely processed the radioactively contaminated trimethyl-metal compounds into metal oxides. The waste stream came from LANL research operations, and had been in storage for seven years, pending treatment options. (authors)

Colby, S.; Turner, Z.; Utley, D. [Pacific EcoSolutions, Inc., 2025 Battelle Boulevard, Richland, Washington 99354 (United States); Duy, C. [Los Alamos National Laboratory - LA-UR-05-8410, Post Office Box 1663 MS J595, Los Alamos, New Mexico 97545 (United States)

2006-07-01T23:59:59.000Z

260

Development and testing of the Minimum Additive Waste Stabilization (MAWS) system for Fernald wastes. Phase 1, Final report  

Science Conference Proceedings (OSTI)

This report presents results of a treatability study for the evaluation of the MAWS process for wastes stored at the Fernald Environmental Management Project (FEMP) site. Wastes included in the study were FEMP Pit 5 sludges, soil-wash fractions, and ion exchange media from a water treatment system supporting a soil washing system. MAWS offers potential for treating a variety of waste streams to produce a more leach resistant waste form at a lower cost than, say, cement stabilization.

Fu, S.S.; Matlack, K.S.; Mohr, R.K.; Brandys, M. Hojaji, H.; Bennett, S.; Ruller, J.; Pegg, I.L. [GTS Duratek, Columbia, MD (United States)

1994-12-01T23:59:59.000Z

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

Developing Automated Methods of Waste Sorting  

SciTech Connect

The U.S. Department of Energy (DOE) analyzed the need complex-wide for remote and automated technologies as they relate to the treatment and disposal of mixed wastes. This analysis revealed that several DOE sites need the capability to open drums containing waste, visually inspect and sort the contents, and finally repackage the containers that are acceptable at a waste disposal facility such as the Waste Isolation Pilot Plant (WIPP) in New Mexico. Conditioning contaminated waste so that it is compatible with the WIPP criteria for storage is an arduous task whether the waste is contact handled (waste having radioactivity levels below 200 mrem/hr) or remote handled. Currently, WIPP non-compliant items are removed from the waste stream manually, at a rate of about one 55-gallon drum per day. Issues relating to contamination-based health hazards as well as repetitive motion health hazards are steering industry towards a more user-friendly, method of conditioning or sorting waste.

Shurtliff, Rodney Marvin

2002-08-01T23:59:59.000Z

262

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

263

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

264

Hanford Tank Waste Residuals  

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

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

265

Waste minimization for commercial radioactive materials users generating low-level radioactive waste. Revision 1  

SciTech Connect

The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature.

Fischer, D.K.; Gitt, M.; Williams, G.A.; Branch, S. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Otis, M.D.; McKenzie-Carter, M.A.; Schurman, D.L. [Science Applications International Corp., Idaho Falls, ID (United States)

1991-07-01T23:59:59.000Z

266

L/O/G/OL/O/G/O Waste Waste  

E-Print Network (OSTI)

L/O/G/OL/O/G/O #12;· Waste Waste · Value () · · Flow #12;Genchi GenbutsuGenchi Genbutsu of waste) Zero Inventory #12;Just in Time in HealthcareJust in Time in Healthcare Takt time (pitch), one · · · · · · · · · · · · · · · · · · 5 WHY · · · RCA · · · 5 WHY · · #12; waste/ value waste/ value

Laksanacharoen, Sathaporn

267

Radioactive waste material disposal  

DOE Patents (OSTI)

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

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

1995-10-24T23:59:59.000Z

268

Radioactive waste material disposal  

DOE Patents (OSTI)

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

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

1995-01-01T23:59:59.000Z

269

Plasma Mass Filters For Nuclear Waste Reprocessing  

SciTech Connect

Practical disposal of nuclear waste requires high-throughput separation techniques. The most dangerous part of nuclear waste is the fission product, which contains the most active and mobile radioisotopes and produces most of the heat. We suggest that the fission products could be separated as a group from nuclear waste using plasma mass filters. Plasmabased processes are well suited to separating nuclear waste, because mass rather than chemical properties are used for separation. A single plasma stage can replace several stages of chemical separation, producing separate streams of bulk elements, fission products, and actinoids. The plasma mass filters may have lower cost and produce less auxiliary waste than chemical processing plants. Three rotating plasma configurations are considered that act as mass filters: the plasma centrifuge, the Ohkawa filter, and the asymmetric centrifugal trap.

Abraham J. Fetterman and Nathaniel J. Fisch

2011-05-26T23:59:59.000Z

270

Method for calcining radioactive wastes  

DOE Patents (OSTI)

This invention relates to a method for the preparation of radioactive wastes in a low leachability form by calcining the radioactive waste on a fluidized bed of glass frit, removing the calcined waste to melter to form a homogeneous melt of the glass and the calcined waste, and then solidifying the melt to encapsulate the radioactive calcine in a glass matrix.

Bjorklund, William J. (Richland, WA); McElroy, Jack L. (Richland, WA); Mendel, John E. (Kennewick, WA)

1979-01-01T23:59:59.000Z

271

Methane generation from waste materials  

DOE Patents (OSTI)

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

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

2010-03-23T23:59:59.000Z

272

Copenhagen Waste Management and Incineration  

E-Print Network (OSTI)

Copenhagen Waste Management and Incineration Florence, April 24 2009 Julie B. Svendsen 24 20092 Presentation · General introduction to Copenhagen Waste Management System · National incentives · Waste Management plan 2012 · Incineration plants #12;Florence, April 24 20093 Copenhagen Waste

Columbia University

273

Waste to Energy Time Activities  

E-Print Network (OSTI)

SEMINAR Waste to Energy Time Activities 9:30-9:40 Brief introduction of participants 9:40-10:10 Presentation of Dr. Kalogirou, "Waste to Energy: An Integral Part of Worldwide Sustainable Waste Management" 10. Sofia Bethanis, "Production of synthetic aggregates for use in structural concrete from waste to energy

Columbia University

274

Contained recovery of oily waste  

DOE Patents (OSTI)

A method is provided for recovering oily waste from oily waste accumulations underground comprising sweeping the oily waste accumulation with hot water to recover said oily waste, wherein said area treated is isolated from surrounding groundwater hydraulically. The hot water may be reinjected after the hot-water displacement or may be treated to conform to any discharge requirements.

Johnson, Jr., Lyle A. (Laramie, WY); Sudduth, Bruce C. (Laramie, WY)

1989-01-01T23:59:59.000Z

275

Boehmite Actual Waste Dissolutions Studies  

SciTech Connect

The U.S. Department of Energy plans to vitrify approximately 60,000 metric tons of high-level waste (HLW) sludge from underground storage tanks at the Hanford Nuclear Reservation. To reduce the volume of HLW requiring treatment, a goal has been set to remove a significant quantity of the aluminum, which comprises nearly 70 percent of the sludge. Aluminum is found in the form of gibbsite, sodium aluminate and boehmite. Gibbsite and sodium aluminate can be easily dissolved by washing the waste stream with caustic. Boehmite, which comprises nearly half of the total aluminum, is more resistant to caustic dissolution and requires higher treatment temperatures and hydroxide concentrations. Samples were taken from four Hanford tanks and homogenized in order to give a sample that is representative of REDOX (Reduction Oxidation process for Pu recovery) sludge solids. Bench scale testing was performed on the homogenized waste to study the dissolution of boehmite. Dissolution was studied at three different hydroxide concentrations, with each concentration being run at three different temperatures. Samples were taken periodically over the 170 hour runs in order to determine leaching kinetics. Results of the dissolution studies and implications for the proposed processing of these wastes will be discussed.

Snow, Lanee A.; Lumetta, Gregg J.; Fiskum, Sandra K.; Peterson, Reid A.

2008-07-15T23:59:59.000Z

276

Certification Plan, low-level waste Hazardous Waste Handling Facility  

SciTech Connect

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

Albert, R.

1992-06-30T23:59:59.000Z

277

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

278

Liquid low level waste management expert system  

SciTech Connect

An expert system has been developed as part of a new initiative for the Oak Ridge National Laboratory (ORNL) systems analysis program. This expert system will aid in prioritizing radioactive waste streams for treatment and disposal by evaluating the severity and treatability of the problem, as well as the final waste form. The objectives of the expert system development included: (1) collecting information on process treatment technologies for liquid low-level waste (LLLW) that can be incorporated in the knowledge base of the expert system, and (2) producing a prototype that suggests processes and disposal technologies for the ORNL LLLW system. 4 refs., 9 figs.

Ferrada, J.J.; Abraham, T.J. (Oak Ridge National Lab., TN (United States)); Jackson, J.R. (Southwest Baptist Univ., Bolivar, MO (USA))

1991-01-01T23:59:59.000Z

279

Feed Materials Production Center waste management plan (Revision to NLCO-1100, R. 6)  

Science Conference Proceedings (OSTI)

In the process of producing uranium metal products used in Department of Energy (DOE) defense programs at other DOE facilities, various types of wastes are generated at the Feed Materials Production Center (FMPC). Process wastes, both generated and stored, are discussed in the Waste Management Plan and include low-level radioactive waste (LLW), mixed hazardous/radioactive waste, and sanitary/industrial waste. Scrap metal waste and wastes requiring special remediation are also addressed in the Plan. The Waste Management Plan identifies the comprehensive programs developed to address safe storage and disposition of all wastes from past, present, and future operations at the FMPC. Waste streams discussed in this Plan are representative of the wastes generated and waste types that concern worker and public health and safety. Budgets and schedules for implementation of waste disposition are also addressed. The waste streams receiving the largest amount of funding include LLW approved for shipment by DOE/ORO to the Nevada Test Site (NTS) (MgF/sub 2/, slag leach filter cake, and neutralized raffinate); remedial action wastes (waste pits, K-65 silo waste); thorium; scrap metal (contaminated and noncontaminated ferrous and copper scrap); construction rubble and soil generated from decontamination and decommissioning of outdated facilities; and low-level wastes that will be handled through the Low-Level Waste Processing and Shipping System (LLWPSS). Waste Management milestones are also provided. The Waste Management Plan is divided into eight major sections: Introduction; Site Waste and Waste Generating Process; Strategy; Projects and Operations; Waste Stream Budgets; Milestones; Quality Assurance for Waste Management; and Environmental Monitoring Program.

Watts, R.E.; Allen, T.; Castle, S.A.; Hopper, J.P.; Oelrich, R.L.

1986-10-15T23:59:59.000Z

280

Tank Waste Strategy Update  

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

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

Note: This page contains sample records for the topic "waste waste stream" 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 Treatment Plant Overview  

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

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

282

ORNL radioactive waste operations  

SciTech Connect

Since its beginning in 1943, ORNL has generated large amounts of solid, liquid, and gaseous radioactive waste material as a by-product of the basic research and development work carried out at the laboratory. The waste system at ORNL has been continually modified and updated to keep pace with the changing release requirements for radioactive wastes. Major upgrading projects are currently in progress. The operating record of ORNL waste operation has been excellent over many years. Recent surveillance of radioactivity in the Oak Ridge environs indicates that atmospheric concentrations of radioactivity were not significantly different from other areas in East Tennesseee. Concentrations of radioactivity in the Clinch River and in fish collected from the river were less than 4% of the permissible concentration and intake guides for individuals in the offsite environment. While some radioactivity was released to the environment from plant operations, the concentrations in all of the media sampled were well below established standards.

Sease, J.D.; King, E.M.; Coobs, J.H.; Row, T.H.

1982-01-01T23:59:59.000Z

283

Handford Waste Division  

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

1 Hanford Waste Diversion SAN Teleconference June 21, 2012 Tom Ferns, DOE-RL 2 Hanford Site Mission The Hanford Site is engaged in one of the largest and most complex environmental...

284

Pioneering Nuclear Waste Disposal  

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

request for further delays After the EPA certified that the WIPP met the standards for disposal of transuranic waste in May 1998, then-New Mexico Attorney General Tom Udall...

285

Vitrification of waste  

DOE Patents (OSTI)

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

Wicks, G.G.

1992-12-31T23:59:59.000Z

286

Treatment of organic waste  

DOE Patents (OSTI)

An organic waste containing at least one element selected from the group consisting of strontium, cesium, iodine and ruthenium is treated to achieve a substantial reduction in the volume of the waste and provide for fixation of the selected element in an inert salt. The method of treatment comprises introducing the organic waste and a source of oxygen into a molten salt bath maintained at an elevated temperature to produce solid and gaseous reaction products. The gaseous reaction products comprise carbon dioxide and water vapor, and the solid reaction products comprise the inorganic ash constituents of the organic waste and the selected element which is retained in the molten salt. The molten salt bath comprises one or more alkali metal carbonates, and may optionally include from 1 to about 25 wt.% of an alkali metal sulfate.

Grantham, LeRoy F. (Calabasas, CA)

1979-01-01T23:59:59.000Z

287

Problems associated with solid wastes from energy systems  

Science Conference Proceedings (OSTI)

Waste streams from many energy-related technologies including coal, oil shale, tar sands, geothermal, oil and gas extraction, and nuclear power generation are reviewed with an emphasis on waste streams from coal and oil shale technologies. This study has two objectives. The first objective is to outline the available information on energy-related solid wastes. Data on chemical composition and hazardous biological characteristics are included, supplemented by regulatory reviews and data on legally designated hazardous waste streams. The second objective is to provide disposal and utilization options. Solid waste disposal and recovery requirements specified under the RCRA are emphasized. Information presented herein should be useful for policy, environmental control, and research and development decision making regarding solid and hazardous wastes from energy production.

Chiu, S.Y.; Fradkin, L.; Barisas, S.; Surles, T.; Morris, S.; Crowther, A.; DeCarlo, V.

1980-09-01T23:59:59.000Z

288

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

289

Medical and Biohazardous Waste Generator's Guide (Revision 2)  

E-Print Network (OSTI)

Biohazardous Waste Training Medical/Biohazardous WasteInspections 7. Forms and Supplies Medical Waste AccumulationLog Ordering Medical Waste Supplies 8. Solid Medical Waste

Waste Management Group

2006-01-01T23:59:59.000Z

290

Certification Plan, Radioactive Mixed Waste Hazardous Waste Handling Facility  

SciTech Connect

The purpose of this plan is to describe the organization and methodology for the certification of radioactive mixed waste (RMW) handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). RMW is low-level radioactive waste (LLW) or transuranic (TRU) waste that is co-contaminated with dangerous waste as defined in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and the Washington State Dangerous Waste Regulations, 173-303-040 (18). This waste is to be transferred to the Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington. This plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF (Section 4); and a list of the current and planned implementing procedures used in waste certification.

Albert, R.

1992-06-30T23:59:59.000Z

291

Reportable Nuclide Criteria for ORNL Waste Management Activities - 13005  

SciTech Connect

The U.S. Department of Energy's Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee generates numerous radioactive waste streams. Many of those streams contain a large number of radionuclides with an extremely broad range of concentrations. To feasibly manage the radionuclide information, ORNL developed a reportable nuclide criteria to distinguish between those nuclides in a waste stream that require waste tracking versus those nuclides of such minimal activity that do not require tracking. The criteria include tracking thresholds drawn from ORNL onsite management requirements, transportation requirements, and relevant treatment and disposal facility acceptance criteria. As a management practice, ORNL maintains waste tracking on a nuclide in a specific waste stream if it exceeds any of the reportable nuclide criteria. Nuclides in a specific waste stream that screen out as non-reportable under all these criteria may be dropped from ORNL waste tracking. The benefit of this criteria is to ensure that nuclides in a waste stream with activities which meaningfully affect safety and compliance are tracked, while documenting the basis for removing certain isotopes from further consideration.

McDowell, Kip [ORNL; Forrester, Tim [ORNL; Saunders, Mark Edward [ORNL

2013-01-01T23:59:59.000Z

292

Recovery of fissile materials from nuclear wastes  

DOE Patents (OSTI)

A process is described for recovering fissile materials such as uranium, and plutonium, and rare earth elements, from complex waste feed material, and converting the remaining wastes into a waste glass suitable for storage or disposal. The waste feed is mixed with a dissolution glass formed of lead oxide and boron oxide resulting in oxidation, dehalogenation, and dissolution of metal oxides. Carbon is added to remove lead oxide, and a boron oxide fusion melt is produced. The fusion melt is essentially devoid of organic materials and halogens, and is easily and rapidly dissolved in nitric acid. After dissolution, uranium, plutonium, and rare earth elements are separated from the acid and recovered by processes such as PUREX or ion exchange. The remaining acid waste stream is vitrified to produce a waste glass suitable for storage or disposal. Potential waste feed materials include plutonium scrap and residue, miscellaneous spent nuclear fuel, and uranium fissile wastes. The initial feed materials may contain mixtures of metals, ceramics, amorphous solids, halides, organic material and other carbon-containing material.

Forsberg, Charles W.

1997-12-01T23:59:59.000Z

293

Recovery of fissile materials from nuclear wastes  

DOE Patents (OSTI)

A process for recovering fissile materials such as uranium, and plutonium, and rare earth elements, from complex waste feed material, and converting the remaining wastes into a waste glass suitable for storage or disposal. The waste feed is mixed with a dissolution glass formed of lead oxide and boron oxide resulting in oxidation, dehalogenation, and dissolution of metal oxides. Carbon is added to remove lead oxide, and a boron oxide fusion melt is produced. The fusion melt is essentially devoid of organic materials and halogens, and is easily and rapidly dissolved in nitric acid. After dissolution, uranium, plutonium and rare earth elements are separated from the acid and recovered by processes such as PUREX or ion exchange. The remaining acid waste stream is vitrified to produce a waste glass suitable for storage or disposal. Potential waste feed materials include plutonium scrap and residue, miscellaneous spent nuclear fuel, and uranium fissile wastes. The initial feed materials may contain mixtures of metals, ceramics, amorphous solids, halides, organic material and other carbon-containing material.

Forsberg, Charles W. (Oak Ridge, TN)

1999-01-01T23:59:59.000Z

294

Idaho Waste Vitrification Facilities Project Vitrified Waste Interim Storage Facility  

SciTech Connect

This feasibility study report presents a draft design of the Vitrified Waste Interim Storage Facility (VWISF), which is one of three subprojects of the Idaho Waste Vitrification Facilities (IWVF) project. The primary goal of the IWVF project is to design and construct a treatment process system that will vitrify the sodium-bearing waste (SBW) to a final waste form. The project will consist of three subprojects that include the Waste Collection Tanks Facility, the Waste Vitrification Facility (WVF), and the VWISF. The Waste Collection Tanks Facility will provide for waste collection, feed mixing, and surge storage for SBW and newly generated liquid waste from ongoing operations at the Idaho Nuclear Technology and Engineering Center. The WVF will contain the vitrification process that will mix the waste with glass-forming chemicals or frit and turn the waste into glass. The VWISF will provide a shielded storage facility for the glass until the waste can be disposed at either the Waste Isolation Pilot Plant as mixed transuranic waste or at the future national geological repository as high-level waste glass, pending the outcome of a Waste Incidental to Reprocessing determination, which is currently in progress. A secondary goal is to provide a facility that can be easily modified later to accommodate storage of the vitrified high-level waste calcine. The objective of this study was to determine the feasibility of the VWISF, which would be constructed in compliance with applicable federal, state, and local laws. This project supports the Department of Energy’s Environmental Management missions of safely storing and treating radioactive wastes as well as meeting Federal Facility Compliance commitments made to the State of Idaho.

Bonnema, Bruce Edward

2001-09-01T23:59:59.000Z

295

Mixed waste focus area alternative technologies workshop  

SciTech Connect

This report documents the Mixed Waste Focus Area (MWFA)-sponsored Alternative Technology Workshop held in Salt Lake City, Utah, from January 24--27, 1995. The primary workshop goal was identifying potential applications for emerging technologies within the Options Analysis Team (OAT) ``wise`` configuration. Consistent with the scope of the OAT analysis, the review was limited to the Mixed Low-Level Waste (MLLW) fraction of DOE`s mixed waste inventory. The Los Alamos team prepared workshop materials (databases and compilations) to be used as bases for participant review and recommendations. These materials derived from the Mixed Waste Inventory Report (MWIR) data base (May 1994), the Draft Site Treatment Plan (DSTP) data base, and the OAT treatment facility configuration of December 7, 1994. In reviewing workshop results, the reader should note several caveats regarding data limitations. Link-up of the MWIR and DSTP data bases, while representing the most comprehensive array of mixed waste information available at the time of the workshop, requires additional data to completely characterize all waste streams. A number of changes in waste identification (new and redefined streams) occurred during the interval from compilation of the data base to compilation of the DSTP data base with the end result that precise identification of radiological and contaminant characteristics was not possible for these streams. To a degree, these shortcomings compromise the workshop results; however, the preponderance of waste data was linked adequately, and therefore, these analyses should provide useful insight into potential applications of alternative technologies to DOE MLLW treatment facilities.

Borduin, L.C.; Palmer, B.A.; Pendergrass, J.A. [Los Alamos National Lab., NM (United States). Technology Analysis Group

1995-05-24T23:59:59.000Z

296

Transporting & Shipping Hazardous Materials at LBNL: Waste -...  

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

Waste: Hazardous, Biohazardous, Medical or Radioactive Do not transport or ship hazardous material wastes off-site. Only Waste Management, Radiation Protection or approved...

297

Nonhazardous Solid Waste Management Regulations & Criteria (Mississippi)  

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

The purpose of the Nonhazardous Solid Waste Management Regulations & Criteria is to establish a minimum State Criteria under the Mississippi Solid Waste Law for all solid waste management...

298

Hazardous Waste Management (Oklahoma) | Department of Energy  

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

treatment and storage of such waste. It also mentions the availability of tax credits for waste facilities. Energy recovery from the destruction of a hazardous waste may be...

299

Annual Transuranic Waste Inventory Report - 2013  

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

contain both combustible and noncombustible waste items. Combustible waste may include wood, plastics, paper, and rags. Noncombustible waste items may include metals, glass,...

300

Bioenergy development from agricultural waste on Northern ...  

Science Conference Proceedings (OSTI)

... Summary This project will convert agricultural waste, including food waste, rice straw, and other organic farm waste to bioethanol through bacterial ...

2011-08-02T23:59:59.000Z

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

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...

302

Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania)  

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

Municipal Waste Planning, Recycling and Waste Reduction Act Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Pennsylvania Program Type Environmental Regulations

303

Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania)  

Open Energy Info (EERE)

Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) No revision has been approved for this page. It is currently under review by our subject matter experts. Jump to: navigation, search Last modified on February 13, 2013. EZFeed Policy Place Pennsylvania Name Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Policy Category Other Policy Policy Type Environmental Regulations Affected Technologies Biomass/Biogas, Coal with CCS, Concentrating Solar Power, Energy Storage, Fuel Cells, Geothermal Electric, Hydroelectric, Hydroelectric (Small), Natural Gas, Nuclear, Solar Photovoltaics, Wind energy Active Policy Yes Implementing Sector State/Province Program Administrator Pennsylvania Department of Environmental Protection

304

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

305

Certification plan transuranic waste: Hazardous Waste Handling Facility  

SciTech Connect

The purpose of this plan is to describe the organization and methodology for the certification of transuranic (TRU) waste handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). The plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Quality Assurance Implementing Management Plan (QAIMP) for the HWBF; and a list of the current and planned implementing procedures used in waste certification.

1992-06-01T23:59:59.000Z

306

Solid Waste and Infectious Waste Regulations (Ohio) | Department of Energy  

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

and Infectious Waste Regulations (Ohio) and Infectious Waste Regulations (Ohio) Solid Waste and Infectious Waste Regulations (Ohio) < Back Eligibility Utility Agricultural Investor-Owned Utility Industrial Municipal/Public Utility Local Government Rural Electric Cooperative Program Info State Ohio Program Type Environmental Regulations Provider Ohio Environmental Protection Agency This chapter of the law that establishes the Ohio Environmental Protection Agency establishes the rules and regulations regarding solid waste. The chapter establishes specific regulations for biomass facilities, which includes permitting, siting, operation, safety guidelines, and closing requirements. Siting regulations include setbacks from waste handling areas for state facilities (1000 feet from jails, schools), requirements for not siting

307

Background chemistry for chemical warfare agents and decontamination processes in support of delisting waste streams at the U.S. Army Dugway Proving Ground, Utah  

SciTech Connect

The State of Utah, Department of Environmental Quality (DEQ), Division of Solid and Hazardous Waste (DSHW), has declared residues resulting from the demilitarization, treatment, cleanup, and testing of military chemical agents to be hazardous wastes. These residues have been designated as corrosive, reactive, toxic, and acute hazardous (Hazardous Waste No. F999). The RCRA regulations (40 Code of Federal Regulations [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. The U.S. Army Test and Evaluation Command (TECOM) believes that certain categories of F999 residues are not hazardous and has obtained assistance from Argonne National Laboratory (Argonne) to make the delisting demonstration. The objective of this project is to delist chemical agent decontaminated residues resulting from materials testing activities and to delist a remediation residue (e.g., contaminated soil). To delist these residues, it must be demonstrated that the residues (1) do not contain hazardous quantities of the listed agents; (2) do not contain hazardous quantities of constituents listed in 40 CFR Part 261, Appendix VIII; (3) do not exhibit other characteristics that could define the residues as hazardous; and (4) do not fail a series of acute toxicity tests. The first phase will focus on a subset of the F999 wastes generated at the U.S. Army Dugway Proving Ground (DPG), where the Army tests the effects of military chemical agents and agent-decontamination procedures on numerous military items. This effort is identified as Phase I of the Delisting Program. Subsequent phases will address other DPG chemical agent decontaminated residues and remediation wastes and similar residues at other installations.

Rosenblatt, D.H.; Small, M.J.; Kimmell, T.A.; Anderson, A.W.

1996-04-01T23:59:59.000Z

308

Focus Sheet | Hazardous Waste Checklist How to be ready for state hazardous waste  

E-Print Network (OSTI)

Focus Sheet | Hazardous Waste Checklist How to be ready for state hazardous waste inspectors. See a hazardous waste inspection. ons, rrosive. n hemicals? ical waste. Waste-like chemicals have als Are you. Are your waste containers properly labeled? us Waste label as soon t Do you accumulate waste in a safe

Wilcock, William

309

The largest radioactive waste glassification  

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

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

310

LANL reaches waste shipment milestone  

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

LANL reaches waste shipment milestone LANL reaches waste shipment milestone LANL reaches waste shipment milestone The Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total. May 31, 2011 A shipment of transuranic waste on its way to the WIPP repository A shipment of transuranic waste on its way to the WIPP repository. Contact Fred deSousa Communicatons Office (505) 665-3430 Email LOS ALAMOS, New Mexico, May 31, 2011 - Los Alamos National Laboratory has reached an important milestone in its campaign to ship transuranic (TRU) waste from Cold War-era nuclear operations to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. This month, the Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total.

311

Mixed waste characterization reference document  

SciTech Connect

Waste characterization and monitoring are major activities in the management of waste from generation through storage and treatment to disposal. Adequate waste characterization is necessary to ensure safe storage, selection of appropriate and effective treatment, and adherence to disposal standards. For some wastes characterization objectives can be difficult and costly to achieve. The purpose of this document is to evaluate costs of characterizing one such waste type, mixed (hazardous and radioactive) waste. For the purpose of this document, waste characterization includes treatment system monitoring, where monitoring is a supplement or substitute for waste characterization. This document establishes a cost baseline for mixed waste characterization and treatment system monitoring requirements from which to evaluate alternatives. The cost baseline established as part of this work includes costs for a thermal treatment technology (i.e., a rotary kiln incinerator), a nonthermal treatment process (i.e., waste sorting, macronencapsulation, and catalytic wet oxidation), and no treatment (i.e., disposal of waste at the Waste Isolation Pilot Plant (WIPP)). The analysis of improvement over the baseline includes assessment of promising areas for technology development in front-end waste characterization, process equipment, off gas controls, and monitoring. Based on this assessment, an ideal characterization and monitoring configuration is described that minimizes costs and optimizes resources required for waste characterization.

1997-09-01T23:59:59.000Z

312

Waste form product characteristics  

SciTech Connect

The Department of Energy has operated nuclear facilities at the Idaho National Engineering Laboratory (INEL) to support national interests for several decades. Since 1953, it has supported the development of technologies for the storage and reprocessing of spent nuclear fuels (SNF) and the resultant wastes. However, the 1992 decision to discontinue reprocessing of SNF has left nearly 768 MT of SNF in storage at the INEL with unspecified plans for future dispositioning. Past reprocessing of these fuels for uranium and other resource recovery has resulted in the production of 3800 M{sup 3} calcine and a total inventory of 7600 M{sup 3} of radioactive liquids (1900 M{sup 3} destined for immediate calcination and the remaining sodium-bearing waste requiring further treatment before calcination). These issues, along with increased environmental compliance within DOE and its contractors, mandate operation of current and future facilities in an environmentally responsible manner. This will require satisfactory resolution of spent fuel and waste disposal issues resulting from the past activities. A national policy which identifies requirements for the disposal of SNF and high level wastes (HLW) has been established by the Nuclear Waste Policy Act (NWPA) Sec.8,(b) para(3)) [1982]. The materials have to be conditioned or treated, then packaged for disposal while meeting US Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) regulations. The spent fuel and HLW located at the INEL will have to be put into a form and package that meets these regulatory criteria. The emphasis of Idaho Chemical Processing Plant (ICPP) future operations has shifted toward investigating, testing, and selecting technologies to prepare current and future spent fuels and waste for final disposal. This preparation for disposal may include mechanical, physical and/or chemical processes, and may differ for each of the various fuels and wastes.

Taylor, L.L.; Shikashio, R.

1995-01-01T23:59:59.000Z

313

Wastes and by-products - alternatives for agricultural use  

Science Conference Proceedings (OSTI)

Top address a growing national problem with generation of wastes and by-products, TVA has been involved for several years with developing and commercializing environmentally responsible practices for eliminating, minimizing, or utilizing various wastes/by-products. In many cases, reducing waste generation is impractical, but the wastes/by-products can be converted into other environmentally sound products. In some instances, conversion of safe, value-added agricultural products in the best or only practical alternative. TVA is currently involved with a diversity of projects converting wastes/by-products into safe, economical, and agriculturally beneficial products. Environmental improvement projects have involved poultry litter, cellulosic wastes, used battery acid, ammonium sulfate fines, lead smelting effluents, deep-welled sulfuric acid/ammonium bisulfate solutions, wood ash, waste magnesium ammonium sulfate slurry from recording tape production, and ammunition plant waste sodium nitrate/ammonium nitrate streams.

Boles, J.L.; Craft, D.J.; Parker, B.R.

1994-10-01T23:59:59.000Z

314

Georgia Waste Control Law (Georgia) | Department of Energy  

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

Waste Control Law (Georgia) Waste Control Law (Georgia) Georgia Waste Control Law (Georgia) < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Georgia Program Type Environmental Regulations Provider Georgia Department of Natural Resources The Waste Control Law makes it unlawful to dump waste in any lakes, streams

315

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

316

Inconsistent pathways of household waste  

Science Conference Proceedings (OSTI)

The aim of this study was to provide policy-makers and waste management planners with information about how recycling programs affect the quantities of specific materials recycled and disposed of. Two questions were addressed: which factors influence household waste generation and pathways? and how reliable are official waste data? Household waste flows were studied in 35 Swedish municipalities, and a wide variation in the amount of waste per capita was observed. When evaluating the effect of different waste collection policies, it was found to be important to identify site-specific factors influencing waste generation. Eleven municipal variables were investigated in an attempt to explain the variation. The amount of household waste per resident was higher in populous municipalities and when net commuting was positive. Property-close collection of dry recyclables led to increased delivery of sorted metal, plastic and paper packaging. No difference was seen in the amount of separated recyclables per capita when weight-based billing for the collection of residual waste was applied, but the amount of residual waste was lower. Sixteen sources of error in official waste statistics were identified and the results of the study emphasize the importance of reliable waste generation and composition data to underpin waste management policies.

Dahlen, Lisa [Division of Waste Science and Technology, Lulea University of Technology, SE, 971 87 Lulea (Sweden)], E-mail: lisa.dahlen@ltu.se; Aberg, Helena [Department of Food, Health and Environment, University of Gothenburg, P.O. Box 12204, SE, 402 42 Gothenburg (Sweden); Lagerkvist, Anders [Division of Waste Science and Technology, Lulea University of Technology, SE, 971 87 Lulea (Sweden); Berg, Per E.O. [HB Anttilator, Stagnellsgatan 3, SE, 652 23, Karlstad (Sweden)

2009-06-15T23:59:59.000Z

317

Waste Form Performance Modeling [Nuclear Waste Management using...  

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...

318

Transuranic Waste Tabletop  

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

Transuranic (TRU) Waste Transuranic (TRU) Waste (Hazard Class 7 Radioactive) Moderator's Version of Tabletop Prepared for the Department of Energy Office of Transportation and Emergency Management 02B00215-07D.p65 This page intentionally left blank table of contents Transportation Emergency Preparedness Program (TEPP) planning tools planning tools planning tools planning tools T T T T Tr r r r ransur ansur ansur ansur ansuranic (TRU) W anic (TRU) W anic (TRU) W anic (TRU) W anic (TRU) Waste aste aste aste aste (Hazar (Hazar (Hazar (Hazar (Hazard Class 7 Radio d Class 7 Radio d Class 7 Radio d Class 7 Radio d Class 7 Radioactiv activ activ activ active) e) e) e) e) Moder Moder Moder Moder Moderat at at at ator' or' or' or' or's V s V s V s V s Version of T ersion of T ersion of T ersion of T ersion of Tablet ablet ablet ablet abletop

319

Pioneering Nuclear Waste Disposal  

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

2 2 3 T he journey to the WIPP began nearly 60 years before the first barrels of transuranic waste arrived at the repository. The United States produced the world's first sig- nificant quantities of transuranic material during the Manhattan Project of World War II in the early 1940s. The government idled its plutonium- producing reactors and warhead manu- facturing plants at the end of the Cold War and scheduled most of them for dismantlement. However, the DOE will generate more transuranic waste as it cleans up these former nuclear weapons facilities. The WIPP is a cor- nerstone of the effort to clean up these facilities by providing a safe repository to isolate transuranic waste in disposal rooms mined out of ancient salt beds, located 2,150 feet below ground. The need for the WIPP

320

Weigh your waste: a sustainable way to reduce waste  

Science Conference Proceedings (OSTI)

An increased concern for the environment has brought about an arena to develop and experiment with new devices to support sustainable design. The 'Weigh Your Waste' (WYW) device will allow the user to monitor their waste charges and provide a platform ... Keywords: bin tax, pay by weight, proenvironmental behavior, recycling, rubbish, sustainable design, trash, waste

Alex A. Gartland; Paulina Piasek

2009-04-01T23:59:59.000Z

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

Swedish nuclear waste efforts  

SciTech Connect

After the introduction of a law prohibiting the start-up of any new nuclear power plant until the utility had shown that the waste produced by the plant could be taken care of in an absolutely safe way, the Swedish nuclear utilities in December 1976 embarked on the Nuclear Fuel Safety Project, which in November 1977 presented a first report, Handling of Spent Nuclear Fuel and Final Storage of Vitrified Waste (KBS-I), and in November 1978 a second report, Handling and Final Storage of Unreprocessed Spent Nuclear Fuel (KBS II). These summary reports were supported by 120 technical reports prepared by 450 experts. The project engaged 70 private and governmental institutions at a total cost of US $15 million. The KBS-I and KBS-II reports are summarized in this document, as are also continued waste research efforts carried out by KBS, SKBF, PRAV, ASEA and other Swedish organizations. The KBS reports describe all steps (except reprocessing) in handling chain from removal from a reactor of spent fuel elements until their radioactive waste products are finally disposed of, in canisters, in an underground granite depository. The KBS concept relies on engineered multibarrier systems in combination with final storage in thoroughly investigated stable geologic formations. This report also briefly describes other activities carried out by the nuclear industry, namely, the construction of a central storage facility for spent fuel elements (to be in operation by 1985), a repository for reactor waste (to be in operation by 1988), and an intermediate storage facility for vitrified high-level waste (to be in operation by 1990). The R and D activities are updated to September 1981.

Rydberg, J.

1981-09-01T23:59:59.000Z

322

Turning Waste into By-Product  

Science Conference Proceedings (OSTI)

This paper studies how a firm can create and capture value by converting a waste stream into a useful and saleable by-product (i.e., implementing by-product synergy (BPS)). We show that BPS creates an operational synergy between two products that are ... Keywords: by-product synergy, environment, operations management, sustainability

Deishin Lee

2012-01-01T23:59:59.000Z

323

Mixed waste focus area technical baseline report. Volume 2  

SciTech Connect

As part of its overall program, the MWFA uses a national mixed waste data set to develop approaches for treating mixed waste that cannot be treated using existing capabilities at DOE or commercial facilities. The current data set was originally compiled under the auspices of the 1995 Mixed Waste Inventory Report. The data set has been updated over the past two years based on Site Treatment Plan revisions and clarifications provided by individual sites. The current data set is maintained by the MWFA staff and is known as MWFA97. In 1996, the MWFA developed waste groupings, process flow diagrams, and treatment train diagrams to systematically model the treatment of all mixed waste in the DOE complex. The purpose of the modeling process was to identify treatment gaps and corresponding technology development needs for the DOE complex. Each diagram provides the general steps needed to treat a specific type of waste. The NWFA categorized each MWFA97 waste stream by waste group, treatment train, and process flow. Appendices B through F provide the complete listing of waste streams by waste group, treatment train, and process flow. The MWFA97 waste strewn information provided in the appendices is defined in Table A-1.

1997-04-01T23:59:59.000Z

324

Chemical aspects of nuclear waste treatment  

SciTech Connect

The chemical aspects of the treatment of gaseous, liquid, and solid wastes are discussed in overview. The role of chemistry and the chemical reactions in waste treatment are emphasized. Waste treatment methods encompass the chemistry of radioactive elements from every group of the periodic table. In most streams, the radioactive elements are present in relatively low concentrations and are often associated with moderately large amounts of process reagents, or materials. In general, it is desirable that waste treatment methods are based on chemistry that is selective for the concentration of radionuclides and does not require the addition of reagents that contribute significantly to the volume of the treated waste. Solvent extraction, ion exchange, and sorbent chemistry play a major role in waste treatment because of the high selectivity provided for many radionuclides. This paper deals with the chemistry of the onsite treatment methods that is typically used at nuclear installations and is not concerned with the chemistry of the various alternative materials proposed for long-term storage of nuclear wastes. The chemical aspects are discussed from a generic point of view in which the chemistry of important radionuclides is emphasized.

Bond, W.D.

1980-01-01T23:59:59.000Z

325

Comprehensive Municipal Solid Waste Management, Resource Recovery...  

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

Municipal Solid Waste Management, Resource Recovery, and Conservation Act (Texas) Comprehensive Municipal Solid Waste Management, Resource Recovery, and Conservation...

326

Transuranic Waste Transportation Working Group Agenda | Department...  

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

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

327

UK Radioactive Waste: Classification, Sources and Management ...  

Science Conference Proceedings (OSTI)

Paper contents outlook: Introduction; Radioactive waste classification; Sources of waste (Nuclear power plant operation/decommissioning, Reprocessing and ...

328

Radioactive waste systems and radioactive effluents  

SciTech Connect

Radioactive waste systems for handling gaseous, liquid, and solid wastes generated at light and pressurized water reactors are described. (TFD)

Row, T.H.

1973-01-01T23:59:59.000Z

329

Waste Disposal (Illinois) | Department of Energy  

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

Waste Disposal (Illinois) Waste Disposal (Illinois) Eligibility Commercial Construction Industrial Utility Program Information Illinois Program Type Environmental Regulations This...

330

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...

331

Waste Management Assistance Act (Iowa)  

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

This section promotes the proper and safe storage, treatment, and disposal of solid, hazardous, and low-level radioactive wastes in Iowa, and calls on Iowans to assume responsibility for waste...

332

The reduction of packaging waste  

Science Conference Proceedings (OSTI)

Nationwide, packaging waste comprises approximately one third of the waste being sent to our solid waste landfills. These wastes range from product and shipping containers made from plastic, glass, wood, and corrugated cardboard to packaging fillers and wraps made from a variety of plastic materials such as shrink wrap and polystyrene peanuts. The amount of packaging waste generated is becoming an important issue for manufacturers, retailers, and consumers. Elimination of packaging not only conserves precious landfill space, it also reduces consumption of raw materials and energy, all of which result in important economic and environmental benefits. At the US Department of Energy-Richland Field Office's (DOE-RL) Hanford Site as well as other DOE sites the generation of packaging waste has added importance. By reducing the amount of packaging waste, DOE also reduces the costs and liabilities associated with waste handling, treatment, storage, and disposal.

Raney, E.A.; McCollom, M.; Hogan, J.

1993-04-01T23:59:59.000Z

333

The reduction of packaging waste  

Science Conference Proceedings (OSTI)

Nationwide, packaging waste comprises approximately one third of the waste being sent to our solid waste landfills. These wastes range from product and shipping containers made from plastic, glass, wood, and corrugated cardboard to packaging fillers and wraps made from a variety of plastic materials such as shrink wrap and polystyrene peanuts. The amount of packaging waste generated is becoming an important issue for manufacturers, retailers, and consumers. Elimination of packaging not only conserves precious landfill space, it also reduces consumption of raw materials and energy, all of which result in important economic and environmental benefits. At the US Department of Energy-Richland Field Office`s (DOE-RL) Hanford Site as well as other DOE sites the generation of packaging waste has added importance. By reducing the amount of packaging waste, DOE also reduces the costs and liabilities associated with waste handling, treatment, storage, and disposal.

Raney, E.A.; McCollom, M.; Hogan, J.

1993-04-01T23:59:59.000Z

334

Delaware Solid Waste Authority (Delaware)  

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

The Delaware Solid Waste Authority (DSWA) runs three landfills, all of which recover methane and generate electricity with a total capacity of 24 MWs. The DSWA Solid Waste Plan includes goals,...

335

Waste Isolation Pilot Plant  

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

Waste Isolation Pilot Plant Waste Isolation Pilot Plant AFFIDAVIT FOR SURVIVING RELATIVE STATE _______________ ) ) ss: __________________ COUNTY OF _____________ ) That I, ________________________, am the _________________________ (Indicate relationship) of ___________________________, who is deceased and make the attached request pursuant to 10 CFR, Section 1008. That the information contained on the attached request is true and correct to the best of my knowledge and belief, and I am signing this authorization subject to the penalties provided in 18 U.S.C. 1001. ____________________________ SIGNATURE NOTARIZATION: SUBSCRIBED and SWORN to before me this ______day of __________, 20_____

336

Explosive Waste Treatment Facility  

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

106 106 Environment a 1 Assessment for th.e Explosive Waste Treatment Facility at Site 300 Lawrence Livermore National Laboratory MASTER November 1995 U.S. Department of Energy Office of Environmental Restoration and Waste Management Washington, DOC. 20585 Portions of this document maly be illegible in electronic image products. Images are produced from the best available original document. Table of Contents 1 . 0 2.0 3 . 0 4.0 5 . 0 6.0 7 . 0 8 . 0 Document Summary .............................................................. 1 Purpose and Need for Agency Action ............................................. 3 Description of the Proposed Action and Alternatives ............................ 4 3.1.1 Location ............................................................. 4

337

Ferrocyanide waste simulant characterization  

Science Conference Proceedings (OSTI)

Ferrocyanide waste simulants were prepared and characterized to help assess safety concerns associated with the ferrocyanide sludges stored in underground single-shell waste tanks at the Hanford Site. Simulants were prepared to represent the variety of ferrocyanide sludges stored in the storage tanks. Physical properties, chemical compositions, and thermodynamic properties of the simulants were determined. The simulants, as produced, were shown to not sustain propagating reactions when subjected to a strong ignition source. Additional testing and evaluations are recommended to assess safety concerns associated with postulated ferrocyanide sludge dry-out and exposure to external ignition sources.

Jeppson, D.W.; Wong, J.J.

1993-01-01T23:59:59.000Z

338

SOLID WASTE MANAGEMENT PLAN  

E-Print Network (OSTI)

ACKNOWLEDGMENTS The Chelan County Public Works Department would like to thank the following organizations and individuals for their assistance in the development of this plan: ? Chelan County’s Solid Waste Council members, past and present, and the municipalities they represent. ? Chelan County’s Solid Waste Advisory Committee members, past and present, and the agencies and businesses they represented. ? the Chelan–Douglas Health District staff. ? Washington Department of Ecology staff. Chelan County residents and businesses also contributed to this document through comments provided during public meetings and through various other channels. The Board of County Commissioners and the Public Works Department gratefully acknowledge this input by the

unknown authors

2007-01-01T23:59:59.000Z

339

Technical area status report for low-level mixed waste final waste forms. Volume 2, Appendices  

Science Conference Proceedings (OSTI)

This report presents information on low-level mixed waste forms.The descriptions of the low-level mixed waste (LLMW) streams that are considered by the Mixed Waste Integrated Program (MWIP) are given in Appendix A. This information was taken from descriptions generated by the Mixed Waste Treatment Program (MWTP). Appendix B provides a list of characteristic properties initially considered by the Final Waste Form (FWF) Working Group (WG). A description of facilities available to test the various FWFs discussed in Volume I of DOE/MWIP-3 are given in Appendix C. Appendix D provides a summary of numerous articles that were reviewed on testing of FWFS. Information that was collected by the tests on the characteristic properties considered in this report are documented in Appendix D. The articles reviewed are not a comprehensive list, but are provided to give an indication of the data that are available.

Mayberry, J.L.; Huebner, T.L. [Science Applications International Corp., Idaho Falls, ID (United States); Ross, W. [Pacific Northwest Lab., Richland, WA (United States); Nakaoka, R. [Los Alamos National Lab., NM (United States); Schumacher, R. [Westinghouse Savannah River Co., Aiken, SC (United States); Cunnane, J.; Singh, D. [Argonne National Lab., IL (United States); Darnell, R. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Greenhalgh, W. [Westinghouse Hanford Co., Richland, WA (United States)

1993-08-01T23:59:59.000Z

340

Revaluing waste in New York City : planning for small-scale compost  

E-Print Network (OSTI)

One-third of the municipal solid waste stream is organic material that, when processed in landfills, produces methane, a highly potent greenhouse gas. Composting is a proven strategy for organic waste management, which ...

Neilson, Sarah (Sarah Jane)

2009-01-01T23:59:59.000Z

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

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

342

Radiological, physical, and chemical characterization of transuranic wastes stored at the Idaho National Engineering Laboratory  

SciTech Connect

This document provides radiological, physical and chemical characterization data for transuranic radioactive wastes and transuranic radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program (PSPI). Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 139 waste streams which represent an estimated total volume of 39,380{sup 3} corresponding to a total mass of approximately 19,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats Plant generated waste forms stored at the INEL are provided to assist in facility design specification.

Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

1994-03-01T23:59:59.000Z

343

WASTE DISPOSAL SECTION CORNELL UNIVERSITY  

E-Print Network (OSTI)

2/07 WASTE DISPOSAL SECTION CORNELL UNIVERSITY PROCEDURE for DISPOSAL of RADIOACTIVE MATERIALS This procedure has been developed to ensure the safety of those individuals who handle radioactive waste identified hazardous waste, or other unusual issues require special consideration. Contact the Department

Manning, Sturt

344

Hazardous Waste Management Keith Williams  

E-Print Network (OSTI)

Hazardous Waste Management Keith Williams DES ­ Environmental Affairs Extension 53163 #12,100 Locally · 1998 Univ of Va $33,990 · 1998 Univ. of MD $0 !!!!! #12;Hazardous Waste Disposal Procedures Hazardous (Chemical) Waste Management in University of Maryland Laboratories o All laboratories and work

Appelbaum, Ian

345

Waste Pickup Form User's Guide  

E-Print Network (OSTI)

Waste Pickup Form User's Guide Updated: 3/13/12 #12;Introduction: Welcome to the Cal State University Fullerton Online Waste Pickup Form User's Guide. In this guide you will learn what you can use phosphorus-32) 3. To request a pickup of universal waste including light bulbs, aerosol cans, batteries

de Lijser, Peter

346

Waste incineration and the community -  

E-Print Network (OSTI)

Waste incineration and the community - The Amsterdam experience The successful community relations strategy followed by the operator of Amsterdam's waste-to- energy plant has convinced the public and other stakeholders of the benefits of incineration for treating the city's waste Thomas McCarthy Article by Thomas Mc

Columbia University

347

RETHINKING WASTE, RECYCLING, AND HOUSEKEEPING  

E-Print Network (OSTI)

RETHINKING WASTE, RECYCLING, AND HOUSEKEEPING EFFICIENCY.EFFICIENCY. A l GA leaner Green #12 t R li Management Recycling Staff The Office of Waste Reduction & Recycling started in The Office of Waste Reduction & Recycling started in 1990, we have 14 full time staff positions. ·We collect over 40

Kelly, Scott David

348

Delivery system for molten salt oxidation of solid waste  

DOE Patents (OSTI)

The present invention is a delivery system for safety injecting solid waste particles, including mixed wastes, into a molten salt bath for destruction by the process of molten salt oxidation. The delivery system includes a feeder system and an injector that allow the solid waste stream to be accurately metered, evenly dispersed in the oxidant gas, and maintained at a temperature below incineration temperature while entering the molten salt reactor.

Brummond, William A. (Livermore, CA); Squire, Dwight V. (Livermore, CA); Robinson, Jeffrey A. (Manteca, CA); House, Palmer A. (Walnut Creek, CA)

2002-01-01T23:59:59.000Z

349

Pioneering Nuclear Waste Disposal  

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

PIONEERING NUCLEAR WASTE DISPOSAL U.S. Department of Energy Carlsbad Area Office February 2000 DOECAO-00-3124 T h e W a s t e I s o l a t i o n P i l o t P l a n t ii Table of...

350

D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE  

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

10 CFR Ch. X (1-1-12 Edition) Pt. 1022 D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE Siting, construction or expansion, and op- eration of disposal facilities for transuranic (TRU) waste and TRU mixed waste (TRU waste also containing hazardous waste as designated in 40 CFR part 261). D12 INCINERATORS Siting, construction, and operation of in- cinerators, other than research and develop- ment incinerators or incinerators for non- hazardous solid waste (as designated in 40 CFR 261.4(b)). PART 1022-COMPLIANCE WITH FLOODPLAIN AND WETLAND EN- VIRONMENTAL REVIEW REQUIRE- MENTS Subpart A-General Sec. 1022.1 Background. 1022.2 Purpose and scope. 1022.3 Policy. 1022.4 Definitions. 1022.5 Applicability. 1022.6 Public inquiries. Subpart B-Procedures for Floodplain and

351

Solid Waste Regulation No. 8 - Solid Waste Composting Facilities (Rhode  

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

Regulation No. 8 - Solid Waste Composting Facilities Regulation No. 8 - Solid Waste Composting Facilities (Rhode Island) Solid Waste Regulation No. 8 - Solid Waste Composting Facilities (Rhode Island) < Back Eligibility Commercial Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Utility Program Info State Rhode Island Program Type Environmental Regulations Provider Department of Environmental Management Facilities which compost putrescible waste and/or leaf and yard waste are subject to these regulations. The regulations establish permitting, registration, and operational requirements for composting facilities. Operational requirements for putrescible waste facilities include siting, distance, and buffer requirements, as well as standards for avoiding harm to endangered species and contamination of air and water sources. Specific

352

WIPP TRANSURANIC WASTE How has the WIPP TRU Waste Inventory Changed  

E-Print Network (OSTI)

of tank waste from the Hanford site that is currently managed as high-level waste. None of this waste has that these Hanford tank wastes will be treated and will eventually be able to meet the WIPP waste acceptance criteria on the Hanford Tank Waste and K-Basin Sludges that were included in the waste inventory for recertifica- tion

353

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

354

Hanford Tank Waste - Near Source Treatment of Low Activity Waste  

SciTech Connect

Treatment and disposition of Hanford Site waste as currently planned consists of I 00+ waste retrievals, waste delivery through up to 8+ miles of dedicated, in-ground piping, centralized mixing and blending operations- all leading to pre-treatment combination and separation processes followed by vitrification at the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The sequential nature of Tank Farm and WTP operations requires nominally 15-20 years of continuous operations before all waste can be retrieved from many Single Shell Tanks (SSTs). Also, the infrastructure necessary to mobilize and deliver the waste requires significant investment beyond that required for the WTP. Treating waste as closely as possible to individual tanks or groups- as allowed by the waste characteristics- is being investigated to determine the potential to 1) defer, reduce, and/or eliminate infrastructure requirements, and 2) significantly mitigate project risk by reducing the potential and impact of single point failures. The inventory of Hanford waste slated for processing and disposition as LAW is currently managed as high-level waste (HLW), i.e., the separation of fission products and other radionuclides has not commenced. A significant inventory ofthis waste (over 20M gallons) is in the form of precipitated saltcake maintained in single shell tanks, many of which are identified as potential leaking tanks. Retrieval and transport (as a liquid) must be staged within the waste feed delivery capability established by site infrastructure and WTP. Near Source treatment, if employed, would provide for the separation and stabilization processing necessary for waste located in remote farms (wherein most ofthe leaking tanks reside) significantly earlier than currently projected. Near Source treatment is intended to address the currently accepted site risk and also provides means to mitigate future issues likely to be faced over the coming decades. This paper describes the potential near source treatment and waste disposition options as well as the impact these options could have on reducing infrastructure requirements, project cost and mission schedule.

Ramsey, William Gene

2013-08-15T23:59:59.000Z

355

Waste Minimization and Pollution Prevention | Department of Energy  

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

Waste Minimization Waste Minimization and Pollution Prevention Waste Minimization and Pollution Prevention Mission The team supports efforts that promote a more sustainable environment and implements pollution prevention activities in accordance with Executive Order (EO) 13423, Strengthening Federal Environmental, Energy, and Transportation Management, and EO 13514, Federal Leadership in Environmental, Energy, and Economic Performance, as approved by LM. The WM/P2 Team advocates environmentally sound waste minimization and pollution prevention practices. Scope Inventory the waste stream. Prevent or reduce pollution and waste at their source. Recycle. Use recycled-content products. Use less toxic or nontoxic products. Key Expectations Monitor and track progress on metrics. Maintain/implement a plan that integrates waste minimization and

356

PASSIVATION LAYER STABILITY OF A METALLIC ALLOY WASTE FORM  

SciTech Connect

Alloy waste form development under the Waste Forms Campaign of the DOE-NE Fuel Cycle Research & Development program includes the process development and characterization of an alloy system to incorporate metal species from the waste streams generated during nuclear fuel recycling. This report describes the tests and results from the FY10 activities to further investigate an Fe-based waste form that uses 300-series stainless steel as the base alloy in an induction furnace melt process to incorporate the waste species from a closed nuclear fuel recycle separations scheme. This report is focused on the initial activities to investigate the formation of oxyhydroxide layer(s) that would be expected to develop on the Fe-based waste form as it corrodes under aqueous repository conditions. Corrosion tests were used to evaluate the stability of the layer(s) that can act as a passivation layer against further corrosion and would affect waste form durability in a disposal environment.

Williamson, M.; Mickalonis, J.; Fisher, D.; Sindelar, R.

2010-08-16T23:59:59.000Z

357

Letter report: Minor component study for low-level radioactive waste glasses  

SciTech Connect

During the waste vitrification process, troublesome minor components in low-level radioactive waste streams could adversely affect either waste vitrification rate or melter life-time. Knowing the solubility limits for these minor components is important to determine pretreatment options for waste streams and glass formulation to prevent or to minimize these problems during the waste vitrification. A joint study between Pacific Northwest Laboratory and Rensselaer Polytechnic Institute has been conducted to determine minor component impacts in low-level nuclear waste glass.

Li, H.

1996-03-01T23:59:59.000Z

358

Accumulated waste characterization work plan  

Science Conference Proceedings (OSTI)

The Portsmouth Gaseous Diffusion Plant (PORTS) as part of the uranium enrichment complex produces enriched uranium for power generation and defense purposes. Since the beginning of diffusion plant operations in 1953, a variety of waste materials and excess equipment has been generated through both normal operations and as part of major system upgrade programs. However, as a result of the closure of former onsite radioactive management facilities and limited onsite and offsite disposal facilities for mixed (hazardous and radioactive) wastes, PORTS has accumulated large quantities of waste awaiting final disposition. These accumulated wastes were estimated in the Accumulated Waste Plan (AWP) to consist of some 21,700 containers of the radioactive, RCRA hazardous, PCB, mixed and asbestos wastes in various storage areas and process buildings with PORTS. In order to proper manage these wastes onsite and prepare for them for ultimate treatment or disposal, a detailed understanding of the waste contents and characteristics must be developed. The strategy for managing and disposing of these wastes was outlined in the AWP. The purpose of this Accumulated Waste Characterization Work Plan (AWCWP) is to provide a detailed plan for characterizing waste containers from the existing PORTS inventory. The AWCWP documents the process and analytical information currently available and describes statistically-based sampling and analyses required to support proper regulatory classification.

Not Available

1992-01-01T23:59:59.000Z

359

Waste Isolation Pilot Plant - Reports  

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

Reports Reports Waste Isolation Pilot Plant Review Report 2013 Review of the Waste Isolation Pilot Plant Work Planning and Control Activities, April 2013 Review Report 2012 Review of Site Preparedness for Severe Natural Phenomena Events at the Waste Isolation Pilot Plant, November 2012 Activity Reports 2011 Orientation Visit to the Waste Isolation Pilot Plant, September 2011 Review Reports 2007 Independent Oversight Inspection of Emergency Management at the Carlsbad Field Office and Waste Isolation Pilot Plant, December 2007 Review Reports 2002 Inspection of Environment, Safety, and Health and Emergency Management at the Waste Isolation Pilot Plant - Summary Report, August 2002 Inspection of Environment, Safety, and Health Management at the Waste Isolation Pilot Plant - Volume I, August 2002

360

Waste Management | Department of Energy  

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

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

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

Environmental waste disposal contracts awarded  

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

Environmental contracts awarded locally Environmental contracts awarded locally Environmental waste disposal contracts awarded locally Three small businesses with offices in Northern New Mexico awarded nuclear waste clean-up contracts. April 3, 2012 Worker moves drums of transuranic (TRU) waste at a staging area A worker stages drums of transuranic waste at Los Alamos National Laboratory's Technical Area 54. the Lap ships such drums to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) in Southern New Mexico. The Lab annually averages about 120 shipments of TRU waste to WIPP. Contact Small Business Office (505) 667-4419 Email "They will be valuable partners in the Lab's ability to dispose of the waste safely and efficiently." Small businesses selected for environmental work at LANL

362

Waste minimization handbook, Volume 1  

Science Conference Proceedings (OSTI)

This technical guide presents various methods used by industry to minimize low-level radioactive waste (LLW) generated during decommissioning and decontamination (D and D) activities. Such activities generate significant amounts of LLW during their operations. Waste minimization refers to any measure, procedure, or technique that reduces the amount of waste generated during a specific operation or project. Preventive waste minimization techniques implemented when a project is initiated can significantly reduce waste. Techniques implemented during decontamination activities reduce the cost of decommissioning. The application of waste minimization techniques is not limited to D and D activities; it is also useful during any phase of a facility`s life cycle. This compendium will be supplemented with a second volume of abstracts of hundreds of papers related to minimizing low-level nuclear waste. This second volume is expected to be released in late 1996.

Boing, L.E.; Coffey, M.J.

1995-12-01T23:59:59.000Z

363

Waste Management | Department of Energy  

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

Cleanup » Waste Management Cleanup » Waste Management Waste Management November 12, 2013 U.S. Department of Energy to Host Press Call on Radioactive Waste Shipment and Disposal On Tuesday, November 12, 2013, the U.S. Department of Energy (DOE) will host a press call to discuss Consolidated Edison Uranium Solidification Project (CEUSP) shipment and disposal plans in Nevada. September 24, 2013 Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with the Pretreatment and

364

Waste Logic(TM): Decommissioning Waste Manager, Version 2.1 and Solid Waste Manager, Version 2.1  

Science Conference Proceedings (OSTI)

Waste Logic(TM) Decommissioning Waste Manager, Version 2.1: Rising program costs and a more competitive business environment have made solid waste management a major cost concern. Effective management of solid waste can reduce long range operating costs for a large nuclear plant by millions of dollars. To assist waste managers in maximizing potential cost savings, EPRI developed the Waste Logic Decommissioning Waste Manager(TM) computer code. It provides a comprehensive methodology for capturing and quan...

2003-03-03T23:59:59.000Z

365

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

366

Waste Isolation Pilot Plant Transuranic Waste Baseline inventory report. Volume 3. Revision 1  

Science Conference Proceedings (OSTI)

This report consists of information related to the waste forms at the WIPP facility from the waste originators. Data for retrievably stored, projected and total wastes are given.

NONE

1995-02-01T23:59:59.000Z

367

Treatment of halogen-containing waste and other waste materials  

DOE Patents (OSTI)

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

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

1997-03-18T23:59:59.000Z

368

Treatment of halogen-containing waste and other waste materials  

DOE Patents (OSTI)

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

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

1997-01-01T23:59:59.000Z

369

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

370

Technetium Waste Form Development Progress Report  

SciTech Connect

The approach being followed to evaluate the use of an iron-based alloy waste form to immobilize the Tc-bearing waste streams generated during the aqueous and electrochemical processing of used fuel that is being studied in the DOE Advanced Fuel Cycle Initiative (AFCI) is presented in this report. The objective is to develop an alloy waste form that provides high waste loading within waste form processing limitations, meets waste form performance requirements for durability and the long-term retention of radionuclides, and can be produced with consistent physical, chemical, and radiological properties that meet regulatory acceptance requirements for disposal. Microanalysis using scanning electron microscopy (SEM) and transmission electron microscopy (TEM) was used to analyze non-radioactive Fe-Mo-Re samples. A sample was prepared for SEM; however, significant unforeseen instrument problems led to delays in conducting the detailed work. The TEM was not available for this particular sample and therefore only preliminary SEM work can be reported. The results are in agreement with previous studies [Ebert 2009]; however, a rhenium-rich region within the Re-Mo phase is clearly visible.

Buck, Edgar C.

2010-02-26T23:59:59.000Z

371

Method and apparatus for incinerating hazardous waste  

DOE Patents (OSTI)

An incineration apparatus and method for disposal of infectious hazardous waste including a fluidized bed reactor containing a bed of granular material. The reactor includes a first chamber, a second chamber, and a vertical partition separating the first and second chambers. A pressurized stream of air is supplied to the reactor at a sufficient velocity to fluidize the granular material in both the first and second chambers. Waste materials to be incinerated are fed into the first chamber of the fluidized bed, the fine waste materials being initially incinerated in the first chamber and subsequently circulated over the partition to the second chamber wherein further incineration occurs. Coarse waste materials are removed from the first chamber, comminuted, and recirculated to the second chamber for further incineration. Any partially incinerated waste materials and ash from the bottom of the second chamber are removed and recirculated to the second chamber for further incineration. This process is repeated until all infectious hazardous waste has been completely incinerated.

Korenberg, Jacob (York, PA)

1990-01-01T23:59:59.000Z

372

WRAP Module 1 waste analysis plan  

Science Conference Proceedings (OSTI)

The purpose of this waste analysis plan is to document the necessary characterization, sampling, screening, analysis, and waste acceptance criteria for waste received at the WRAP Module 1. Waste expected to be received at WRAP Module 1 includes newly generated and retrieved waste. The newly generated waste will undergo verification prior to treatment, storage, or disposal. Retrieved waste from the burial grounds or above ground storage will undergo further characterization (as needed), treatment, supercompaction, and repackaging

Mayancsik, B.A.

1995-09-22T23:59:59.000Z

373

The Potential of Cellulosic Ethanol Production from Municipal Solid Waste: A Technical and Economic Evaluation  

E-Print Network (OSTI)

process streams. Handb. Bioethanol:395-415. 10. Ehrman T.solid waste used as bioethanol sources and its relatedof cellulosic biomass into bioethanol as an alternative

Shi, Jian; Ebrik, Mirvat; Yang, Bin; Wyman, Charles E.

2009-01-01T23:59:59.000Z

374

Secondary waste form testing : ceramicrete phosphate bonded ceramics.  

Science Conference Proceedings (OSTI)

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

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

2011-06-21T23:59:59.000Z

375

Municipal Solid Waste:  

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

Methodology for Allocating Municipal Solid Waste Methodology for Allocating Municipal Solid Waste to Biogenic and Non-Biogenic Energy May 2007 Energy Information Administration Office of Coal, Nuclear, Electric and Alternate Fuels U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the U.S. Department of Energy. The information contained herein should be attributed to the Energy Information Administration and should not be construed as advocating or reflecting any policy of the Department of Energy or any other organization. Contact This report was prepared by staff of the Renewable Information Team, Coal, Nuclear, and Renewables Division, Office of Coal, Nuclear, Electric and Alternate Fuels.

376

Tritium waste package  

DOE Patents (OSTI)

A containment and waste package system for processing and shipping tritium xide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen add oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB.

Rossmassler, Rich (Cranbury, NJ); Ciebiera, Lloyd (Titusville, NJ); Tulipano, Francis J. (Teaneck, NJ); Vinson, Sylvester (Ewing, NJ); Walters, R. Thomas (Lawrenceville, NJ)

1995-01-01T23:59:59.000Z

377

Tritium waste package  

DOE Patents (OSTI)

A containment and waste package system for processing and shipping tritium oxide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB adsorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen and oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB.

Rossmassler, R.; Ciebiera, L.; Tulipano, F.J.; Vinson, S.; Walters, R.T.

1994-12-31T23:59:59.000Z

378

Tritium waste package  

DOE Patents (OSTI)

A containment and waste package system for processing and shipping tritium oxide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within the outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen and oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB. 1 fig.

Rossmassler, R.; Ciebiera, L.; Tulipano, F.J.; Vinson, S.; Walters, R.T.

1995-11-07T23:59:59.000Z

379

Waste | OpenEI  

Open Energy Info (EERE)

Waste Waste Dataset Summary Description The Planning Database Project provides the UK Department of Energy and Climate Change (DECC) with regular data to track progress towards achieving EU targets for electricity generation from renewable energy (RE) sources. Extracts from the database are available each month. Information collected in the database includes: name, location and installed capacity of RE projects over 0.1MW; environmental designations; planning status; and construction status. Included here is the October 2010 Progress Datasheet, and an extract from December, 15, 2010 (i.e. Source UK Department of Energy and Climate Change (DECC) Date Released December 15th, 2010 (3 years ago) Date Updated Unknown Keywords biomass co-firing installed capacity

380

Standard Guide for Preparing Waste Management Plans for Decommissioning Nuclear Facilities  

E-Print Network (OSTI)

1.1 This guide addresses the development of waste management plans for potential waste streams resulting from decommissioning activities at nuclear facilities, including identifying, categorizing, and handling the waste from generation to final disposal. 1.2 This guide is applicable to potential waste streams anticipated from decommissioning activities of nuclear facilities whose operations were governed by the Nuclear Regulatory Commission (NRC) or Agreement State license, under Department of Energy (DOE) Orders, or Department of Defense (DoD) regulations. 1.3 This guide provides a description of the key elements of waste management plans that if followed will successfully allow for the characterization, packaging, transportation, and off-site treatment or disposal, or both, of conventional, hazardous, and radioactive waste streams. 1.4 This guide does not address the on-site treatment, long term storage, or on-site disposal of these potential waste streams. 1.5 This standard does not purport to address ...

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

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

The First Recovery Act Funded Waste Shipment depart from the...  

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

The First Recovery Act Funded Waste Shipment departs from the Advanced Mixed Waste Treatment Facility A shipment of mixed low-level waste left DOEs Advanced Mixed Waste...

382

Nuclear Waste Policy Act Signed | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

> Nuclear Waste Policy Act Signed Nuclear Waste Policy Act Signed January 07, 1983 Washington, DC Nuclear Waste Policy Act Signed President Reagan signs the Nuclear Waste...

383

Mixed Waste Recycling Exemption  

Science Conference Proceedings (OSTI)

As part of an ongoing integrated mixed waste program, EPRI has documented the process for obtaining state approval to apply the Resource Conservation and Recovery Act (RCRA) recycling exemption. This report examines the regulatory basis for the recycling exemption and the strategy for designing and operating a recycling facility to meet that exemption. Specifically addressed is the process of submitting an actual recycling exemption request to an RCRA authorized state and potential roadblocks utilities m...

1998-11-30T23:59:59.000Z

384

Cooling tower waste reduction  

SciTech Connect

At Lawrence Livermore National Laboratory (LLNL), the two main cooling tower systems (central and northwest) were upgraded during the summer of 1997 to reduce the generation of hazardous waste. In 1996, these two tower systems generated approximately 135,400 lbs (61,400 kg) of hazardous sludge, which is more than 90 percent of the hazardous waste for the site annually. At both, wet decks (cascade reservoirs) were covered to block sunlight. Covering the cascade reservoirs reduced the amount of chemical conditioners (e.g. algaecide and biocide), required and in turn the amount of waste generated was reduced. Additionally, at the northwest cooling tower system, a sand filtration system was installed to allow cyclical filtering and backflushing, and new pumps, piping, and spray nozzles were installed to increase agitation. the appurtenance upgrade increased the efficiency of the cooling towers. The sand filtration system at the northwest cooling tower system enables operators to continuously maintain the cooling tower water quality without taking the towers out of service. Operational costs (including waste handling and disposal) and maintenance activities are compared for the cooling towers before and after upgrades. Additionally, the effectiveness of the sand filter system in conjunction with the wet deck covers (northwest cooling tower system), versus the cascade reservoir covers alone (south cooling tower south) is discussed. the overall expected return on investment is calculated to be in excess of 250 percent. this upgrade has been incorporated into the 1998 DOE complex-wide water conservation project being led by Sandia National Laboratory/Albuquerque.

Coleman, S.J.; Celeste, J.; Chine, R.; Scott, C.

1998-05-01T23:59:59.000Z

385

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

386

Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage  

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

Disposal, Hazardous Waste Management Act, Underground Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) < Back Eligibility Agricultural Commercial Construction Developer Fuel Distributor Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Municipal/Public Utility Nonprofit Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Tribal Government Utility Program Info State Tennessee Program Type Environmental Regulations Siting and Permitting Provider Tennessee Department Of Environment and Conservation The Solid Waste Disposal Laws and Regulations are found in Tenn. Code 68-211. These rules are enforced and subject to change by the Public Waste Board (PWB), which is established by the Division of Solid and Hazardous

387

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.

388

Recovery of transplutonium elements from nuclear reactor waste  

DOE Patents (OSTI)

A method of separating actinide values from nitric acid waste solutions resulting from reprocessing of irradiated nuclear fuels comprises oxalate precipitation of the major portion of actinide and lanthanide values to provide a trivalent fraction suitable for subsequent actinide/lanthanide partition, exchange of actinide and lanthanide values in the supernate onto a suitable cation exchange resin to provide an intermediate-lived raffinate waste stream substantially free of actinides, and elution of the actinide values from the exchange resin. The eluate is then used to dissolve the trivalent oxalate fraction prior to actinide/lanthanide partition or may be combined with the reprocessing waste stream and recycled.

Campbell, David O. (Oak Ridge, TN); Buxton, Samuel R. (Wartburg, TN)

1977-05-24T23:59:59.000Z

389

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

390

Mediated electrochemical hazardous waste destruction  

SciTech Connect

There are few permitted processes for mixed waste (radioactive plus chemically hazardous) treatment. We are developing electrochemical processes that convert the toxic organic components of mixed waste to water, carbon dioxide, an innocuous anions such as chloride. Aggressive oxidizer ions such as Ag{sup 2+} or Ce{sup +4} are produced at an anode. These can attack the organic molecules directly. They can also attack water which yields hydroxyl free radicals that in turn attack the organic molecules. The condensed (i.e., solid and/or liquid) effluent streams contain the inorganic radionuclide forms. These may be treated with existing technology and prepared for final disposal. Kinetics and the extent of destruction of some toxic organics have been measured. Depending on how the process is operated, coulombic efficiency can be nearly 100%. In addition, hazardous organic materials are becoming very expensive to dispose of and when they are combined with transuranic radioactive elements no processes are presently permitted. Mediated electrochemical oxidation is an ambient-temperature aqueous-phase process that can be used to oxidize organic components of mixed wastes. Problems associated with incineration, such as high-temperature volatilization of radionuclides, are avoided. Historically, Ag (2) has been used as a mediator in this process. Fe(6) and Co(3) are attractive alternatives to Ag(2) since they form soluble chlorides during the destruction of chlorinated solvents. Furthermore, silver itself is a toxic heavy metal. Quantitative data has been obtained for the complete oxidation of ethylene glycol by Fe(6) and Co(3). Though ethylene glycol is a nonhalogenated organic, this data has enabled us to make direct comparisons of activities of Fe(6) and Co(3) with Ag(2). Very good quantitative data for the oxidation of ethylene glycol by Ag(2) had already been collected. 4 refs., 6 figs.

Hickman, R.G.; Farmer, J.C.; Wang, F.T.

1991-08-01T23:59:59.000Z

391

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

Science Conference Proceedings (OSTI)

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

Hagstrom, T.

1998-04-01T23:59:59.000Z

392

Technical area status report for waste destruction and stabilization  

SciTech Connect

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

Dalton, J.D.; Harris, T.L.; DeWitt, L.M. [Science Applications International Corp., Idaho Falls, ID (United States)

1993-08-01T23:59:59.000Z

393

Treatability study of aqueous, land disposal restricted mixed wastes  

SciTech Connect

Treatment studies have been completed on two aqueous waste streams at the Mixed Waste Storage Facility that are classified as land disposal restricted. Both wastes had mercury and lead as characteristic hazardous constituents. Samples from one of these wastes, composed of mercury and lead sulfide particles along with dissolved mercury and lead, was successfully treated by decanting, filtering, and ion exchanging. The effluent water had an average level of 0.003 and 0.025 mg/L of mercury and lead, respectively. These values are well below the targeted RCRA limits of 0.2 mg/L mercury and 5.0 mg/L lead. An acidic stream, containing the same hazardous metals, was also successfully treated using a treatment process of precipitation, filtering, and then ion exchange. Treatment of another waste was not completely successful, presumably because of the interference of a chelating agent.

Haefner, D.R.

1992-12-01T23:59:59.000Z

394

Waste Treatment and Immobilation Plant HLW Waste Vitrification...  

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

compounds VSL Vitreous State Laboratory of the Catholic University of America WESP Wet Electrostatic Precipitator WGI Washington Group International WTP Waste Treatment and...

395

Tank waste chemistry: A new understanding of waste aging  

SciTech Connect

There is concern about the risk of uncontrolled exothermic reaction(s) in Hanford Site waste tanks containing NO{sub 3}{sup {minus}}/NO{sub 2} based salts and/or metal hydroxide sludges in combination with organics or ferrocyanides. However, gradual oxidation of the waste in the tanks to less reactive species appears to have reduced the risk. In addition, wastes sampled to date contain sufficiently large quantities of water so that propagation reactions are highly unlikely. This paper investigates various aspects of the aging of Hanford tank wastes.

Babad, H. [Westinghouse Hanford Co., Richland, WA (United States); Camaioni, D.M.; Lilga, M.A.; Samuels, W.D.; Strachan, D.M. [Pacific Northwest Lab., Richland, WA (United States)

1993-02-01T23:59:59.000Z

396

Exploratory Study of Waste Generation and Waste Minimization in Sweden.  

E-Print Network (OSTI)

?? The current thesis presents an exploratory study on municipal solid waste generation and minimization in Sweden, with a focus on their connection to basic… (more)

Kuslyaykina, Dina

2013-01-01T23:59:59.000Z

397

Steel-Based Alloy Waste Forms for Reprocessing Wastes  

Science Conference Proceedings (OSTI)

... although the release of some radionuclides is limited by the solubilities of the ... Hot Isostatic Pressing of Chlorine-Containing Plutonium Residues and Wastes.

398

Waste/By-Product Hydrogen  

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

WASTE/BY-PRODUCT HYDROGEN WASTE/BY-PRODUCT HYDROGEN Ruth Cox DOE/DOD Workshop January 13, 2011 January 13, 2011 Fuel Cell and Hydrogen Energy Association The Fuel Cell and Hydrogen Energy Association FCHEA ƒ Trade Association for the industry ƒ Member driven - Market focused ƒ Developers, suppliers, customers, nonprofits, government Ad ƒ Advocacy ƒ Safety and standardization ƒ Education ƒ Strategic Alliances Fuel Cell and Hydrogen Energy Association O M b Our Members 5 W t /B d t H d Waste/By-product Hydrogen Overview Overview ƒ Growing populations, rising standards of living, and increased urbanization leads to a escalating volume of waste leads to a escalating volume of waste. ƒ Huge volumes of waste are collected in dumps, creating a major environmental issue. ƒ ƒ Wastewater treatment plants generate noxious gasses that are released in Wastewater treatment plants generate noxious gasses that are released in

399

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

400

Waste Management | Department of Energy  

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

July 27, 2011 July 27, 2011 End of Year 2010 SNF & HLW Inventories Map of the United States of America that shows the location of approximately 64,000 MTHM of Spent Nuclear Fuel (SNF) & 275 High-Level Radioactive Waste (HLW) Canisters. July 27, 2011 FY 2007 Total System Life Cycle Cost, Pub 2008 The Analysis of the Total System Life Cycle Cost (TSLCC) of the Civilian Radioactive Waste Management Program presents the Office of Civilian Radioactive Waste Management's (OCRWM) May 2007 total system cost estimate for the disposal of the Nation's spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The TSLCC analysis provides a basis for assessing the adequacy of the Nuclear Waste Fund (NWF) Fee as required by Section 302 of the Nuclear Waste Policy Act of 1982 (NWPA), as amended.

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

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

402

Optimizing Organic Waste to Energy Operations  

Science Conference Proceedings (OSTI)

A waste-to-energy firm that recycles organic waste with energy recovery performs two environmentally beneficial functions: it diverts waste from landfills and it produces renewable energy. At the same time, the waste-to-energy firm serves and collects ... Keywords: environment, operating strategy, organic waste to energy, regulation, sustainability

Bar?? Ata; Deishin Lee; Mustafa H. Tongarlak

2012-04-01T23:59:59.000Z

403

What is Hazardous Hazardous waste is  

E-Print Network (OSTI)

What is Hazardous Waste? Hazardous waste is any product charac- terized or labeled as toxic, reactive, cor- rosive, flammable, combustible that is unwanted, dis- carded or no longer useful. This waste may be harmful to human health and/ or the environment. Hazardous Waste Disposal EH&S x7233 E-Waste

de Lijser, Peter

404

Low Temperature Waste Energy Recovery at Chemical Plants and Refineries  

E-Print Network (OSTI)

Technologies to economically recover low-temperature waste energy in chemical plants and refineries are the holy grail of industrial energy efficiency. Low temperature waste energy streams were defined by the Texas Industries of the Future Chemical and Refining Sectors Advisory Committee as streams with a temperature below 400 degrees F. Their waste energy streams were also characterized as to state, flow rate, heat content, source and temperature. These criteria were then used to identify potential candidates of waste heat recovery technologies that might have an application in these industries. Four technologies that met the criteria of the Advisory Committee included: organic rankine cycle (ORC), absorption refrigeration and chilling, Kalina cycle, and fuel cell technologies. This paper characterizes each of these technologies, technical specifications, limitations, potential costs/ payback and commercialization status as was discussed in the Technology Forum held in Houston, TX in May 2012 (TXIOF 2012).

Ferland, K.; papar, R.; Quinn, J.; Kumar, S.

2013-01-01T23:59:59.000Z

405

WRPS MEETING THE CHALLENGE OF TANK WASTE  

SciTech Connect

Washington River Protection Solutions (WRPS) is the Hanford tank operations contractor, charged with managing one of the most challenging environmental cleanup projects in the nation. The U.S. Department of Energy hired WRPS to manage 56 million gallons of high-level radioactive waste stored in 177 underground tanks. The waste is the legacy of 45 years of plutonium production for the U. S. nuclear arsenal. WRPS mission is three-fold: safely manage the waste until it can be processed and immobilized; develop the tools and techniques to retrieve the waste from the tanks, and build the infrastructure needed to deliver the waste to the Waste Treatment Plant (WTP) when it begins operating. WTP will 'vitrify' the waste by mixing it with silica and other materials and heating it in an electric melter. Vitrification turns the waste into a sturdy glass that will isolate the radioactivity from the environment. It will take more than 20 years to process all the tank waste. The tank waste is a complex highly radioactive mixture of liquid, sludge and solids. The radioactivity, chemical composition of the waste and the limited access to the underground storage tanks makes retrieval a challenge. Waste is being retrieved from aging single-shell tanks and transferred to newer, safer double-shell tanks. WRPS is using a new technology known as enhanced-reach sluicing to remove waste. A high-pressure stream of liquid is sprayed at 100 gallons per minute through a telescoping arm onto a hard waste layer several inches thick covering the waste. The waste is broken up, moved to a central pump suction and removed from the tank. The innovative Mobile Arm Retrieval System (MARS) is also being used to retrieve waste. MARS is a remotely operated, telescoping arm installed on a mast in the center of the tank. It uses multiple technologies to scrape, scour and rake the waste toward a pump for removal. The American Reinvestment and Recovery Act (ARRA) provided nearly $326 million over two-and-a-half years to modernize the infrastructure in Hanford's tank farms. WRPS issued 850 subcontracts totaling more than $152 million with nearly 76 percent of that total awarded to small businesses. WRPS used the funding to upgrade tank farm infrastructure, develop technologies to retrieve and consolidate tank waste and extend the life of two critical operating facilities needed to feed waste to the WTP. The 222-S Laboratory analyzes waste to support waste retrievals and transfers. The laboratory was upgraded to support future WTP operations with a new computer system, new analytical equipment, a new office building and a new climate-controlled warehouse. The 242-A Evaporator was upgraded with a control-room simulator for operator training and several upgrades to aging equipment. The facility is used to remove liquid from the tank waste, creating additional storage space, necessary for continued waste retrievals and WTP operation. The One System Integrated Project Team is ajoint effort ofWRPS and Bechtel National to identify and resolve common issues associated with commissioning, feeding and operating the Waste Treatment Plant. Two new facilities are being designed to support WTP hot commlsslomng. The Interim Hanford Storage project is planned to store canisters of immobilized high-level radioactive waste glass produced by the vitrification plant. The facility will use open racks to store the 15-foot long, two-foot diameter canisters of waste, which require remote handling. The Secondary Liquid Waste Treatment Project is a major upgrade to the existing Effluent Treatment Facility at Hanford so it can treat about 10 million gallons of liquid radioactive and hazardous effluent a year from the vitrification plant. The One System approach brings the staff of both companies together to identify and resolve WTP safety issues. A questioning attitude is encouraged and an open forum is maintained for employees to raise issues. WRPS is completing its mission safely with record-setting safety performance. Since WRPS took over the Hanford Tank Operations Contract in October 2

BRITTON JC

2012-02-21T23:59:59.000Z

406

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

SciTech Connect

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

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

1996-12-01T23:59:59.000Z

407

WEB RESOURCE: Nuclear Waste Disposal  

Science Conference Proceedings (OSTI)

May 10, 2007 ... The complete "Yucca Mountain Resource Book" is also available for download at this site. Citation: Nuclear Waste Disposal. 2007. Nuclear ...

408

Solid Waste Management Act (Pennsylvania)  

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

This Act provides for the planning and regulation of solid waste storage, collection, transportation, processing, treatment, and disposal. It requires that municipalities submit plans for municipal...

409

Chernobyl’s waste site  

Science Conference Proceedings (OSTI)

An analysis of the prospects for using the Chernobyl exclusion zone for development of a spent fuel store, waste disposal site and other nuclear facilities.

Schmieman, Eric A.; Paskevych, Sergiy; Sizov, Andrey; Batiy, Valeriy

2007-02-15T23:59:59.000Z

410

Next Generation Waste Glass Melters  

activities as described in EM Tank Waste R&D Plan. Melter project in support of this activity. Facets of WTP processing being investigated/enhanced include:

411

Waste disposal and renewable resources.  

E-Print Network (OSTI)

?? Purpose/aim: The purpose of this dissertation is to find out the effect of waste disposal on environment and to explore the effect of renewable… (more)

Hai, Qu; PiaoYi, Sun

2013-01-01T23:59:59.000Z

412

Nuclear waste incineration technology status  

Science Conference Proceedings (OSTI)

The incinerators developed and/or used for radioactive waste combustion are discussed and suggestions are made for uses of incineration in radioactive waste management programs and for incinerators best suited for specific applications. Information on the amounts and types of radioactive wastes are included to indicate the scope of combustible wastes being generated and in existence. An analysis of recently developed radwaste incinerators is given to help those interested in choosing incinerators for specific applications. Operating information on US and foreign incinerators is also included to provide additional background information. Development needs are identified for extending incinerator applications and for establishing commercial acceptance.

Ziegler, D.L.; Lehmkuhl, G.D.; Meile, L.J.

1981-07-15T23:59:59.000Z

413

Drilling Waste Management Information System  

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

The Drilling Waste Management Information System is an online resource for technical and regulatory information on practices for managing drilling muds and cuttings, including...

414

Waste Bakery on diet Sheep.  

E-Print Network (OSTI)

??This work aimed to evaluate the effects of inclusion of bakery waste (BW) in sheep diets on intake, apparent digestibility, balance of nitrogen compounds and… (more)

Almira Biazon França

2010-01-01T23:59:59.000Z

415

Treatment of mercury containing waste  

DOE Patents (OSTI)

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

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

2002-01-01T23:59:59.000Z

416

FAQS Reference Guide – Waste Management  

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

This reference guide addresses the competency statements in the January 2003 edition of DOE-STD-1159-2003, Waste Management Functional Area Qualification Standard.

417

Waste Clean-up 1  

Science Conference Proceedings (OSTI)

... These figures are concepts of the Waste Retrieval System and Deployment for the Hanford, Washington tank farm, specifically focused on tank C ...

2011-09-30T23:59:59.000Z

418

Challenges of Nuclear Waste Vitrification  

Science Conference Proceedings (OSTI)

The US DOE has developed glass property-composition models to control glass compositions for HLW vitrification at Hanford Waste Treatment & Immobilization ...

419

Transuranic contaminated waste form characterization and data base  

SciTech Connect

This report outlines the sources, quantities, characteristics and treatment of transuranic wastes in the United States. This document serves as part of the data base necessary to complete preparation and initiate implementation of transuranic wastes, waste forms, waste container and packaging standards and criteria suitable for inclusion in the present NRC waste management program. No attempt is made to evaluate or analyze the suitability of one technology over another. Indeed, by the nature of this report, there is little critical evaluation or analysis of technologies because such analysis is only appropriate when evaluating a particular application or transuranic waste streams. Due to fiscal restriction, the data base is developed from a myriad of technical sources and does not necessarily contain operating experience and the current status of all technologies. Such an effort was beyond the scope of this report.

McArthur, W.C.; Kniazewycz, B.G.

1980-07-01T23:59:59.000Z

420

DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation  

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

ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment October 3, 2011 - 12:00pm Addthis DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment CARLSBAD, N.M. - The Waste Isolation Pilot Plant (WIPP) received its

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


421

DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation  

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

DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment October 3, 2011 - 12:00pm Addthis DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment CARLSBAD, N.M. - The Waste Isolation Pilot Plant (WIPP) received its

422

Waste IncIneratIon and Waste PreventIon  

E-Print Network (OSTI)

disposing of waste, it also makes consider- able amounts of energy available in the form of electricity) of electricity and 17 TWh of heat, equivalent to the supply required by a major city like Berlin. This energy can . This is equivalent to the annual CO2 emissions of some 1.6 million passenger cars. This means that waste incineration

423

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

424

Energy implications of the thermal recovery of biodegradable municipal waste materials in the United Kingdom  

SciTech Connect

Highlights: > Energy balances were calculated for the thermal treatment of biodegradable wastes. > For wood and RDF, combustion in dedicated facilities was the best option. > For paper, garden and food wastes and mixed waste incineration was the best option. > For low moisture paper, gasification provided the optimum solution. - Abstract: Waste management policies and legislation in many developed countries call for a reduction in the quantity of biodegradable waste landfilled. Anaerobic digestion, combustion and gasification are options for managing biodegradable waste while generating renewable energy. However, very little research has been carried to establish the overall energy balance of the collection, preparation and energy recovery processes for different types of wastes. Without this information, it is impossible to determine the optimum method for managing a particular waste to recover renewable energy. In this study, energy balances were carried out for the thermal processing of food waste, garden waste, wood, waste paper and the non-recyclable fraction of municipal waste. For all of these wastes, combustion in dedicated facilities or incineration with the municipal waste stream was the most energy-advantageous option. However, we identified a lack of reliable information on the energy consumed in collecting individual wastes and preparing the wastes for thermal processing. There was also little reliable information on the performance and efficiency of anaerobic digestion and gasification facilities for waste.

Burnley, Stephen, E-mail: s.j.burnley@open.ac.uk [Open University, Walton Hall, Milton Keynes MK7 6AA (United Kingdom); Phillips, Rhiannon, E-mail: rhiannon.jones@environment-agency.gov.uk [Strategy Unit, Welsh Assembly Government, Ty Cambria, 29 Newport Road, Cardiff CF24 0TP (United Kingdom); Coleman, Terry, E-mail: terry.coleman@erm.com [Environmental Resources Management Ltd, Eaton House, Wallbrook Court, North Hinksey Lane, Oxford OX2 0QS (United Kingdom); Rampling, Terence, E-mail: twa.rampling@hotmail.com [7 Thurlow Close, Old Town Stevenage, Herts SG1 4SD (United Kingdom)

2011-09-15T23:59:59.000Z

425

WIPP Documents - Hazardous Waste Facility Permit (RCRA)  

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

of Energy to manage, store, and dispose of contact-handled and remote-handled transuranic mixed waste at the Waste Isolation Pilot Plant. Mixed waste contains radioactive and...

426

Options for Handling Noncombustion Waste: Third Edition  

Science Conference Proceedings (OSTI)

Utilities produce a wide variety of noncombustion wastes from generating and distributing electricity as well as from associated support operations. This manual addresses the management of 23 utility noncombustion wastes and describes options for managing these wastes.

1995-07-26T23:59:59.000Z

427

Nuclear Waste Policy Act | Department of Energy  

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

Nuclear Waste Policy Act Nuclear Waste Policy Act Document on the Nuclear Waste Policy Act of 1982 An Act to provide for the development of repositories for the disposal of...

428

Waste Minimization Plan Colorado School of Mines  

E-Print Network (OSTI)

Waste Minimization Plan Colorado School of Mines Prepared by: Environmental Health and Safety Department Revised February 2008 #12;Waste Minimization Plan Table of Contents Policy Statement Based Chemical Inventory and Database................................................4 Centralized Waste

429

Hazardous Waste Management Standards and Regulations (Kansas)  

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

This act states the standards and regulations for the management of hazardous waste. No person shall construct, modify or operate a hazardous waste facility or otherwise dispose of hazardous waste...

430

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

431

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

432

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

433

NUCLEAR WASTE CONSULTANTS, INC.  

E-Print Network (OSTI)

Attached please find the Subtask 1.2 Management, prepared by Water, Waste bibliographical information relevant on NNWSI, now comprising 356 titles. scheduled, semi-annual update report contract. Update Report: Data Inventory and and Land (WWL). The report presents the to the all documents in the WWL library Please note that this is the last for Subtask 1.2 under the current The WWL report has received a managerial review by M. Logsdon (NWC), and the report was prepared under WWL's QA procedures, consistent with the NWC QA-manual. 009-1.2-- NNWSI DATABASE- Aucust IS- 19M-2 Auou~~~~ ~ _ _ _ 5._,1_88

Technical Review Branch

1988-01-01T23:59:59.000Z

434

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

435

Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility  

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

6 6 Technology Readiness Assessment for the Waste Treatment and Immobilization Plant (WTP) HLW Waste Vitrification Facility L. Holton D. Alexander C. Babel H. Sutter J. Young August 2007 Prepared by the U.S. Department of Energy Office of River Protection Richland, Washington, 99352 07-DESIGN-046 Technology Readiness Assessment for the Waste Treatment and Immobilization Plant (WTP) HLW Waste Vitrification Facility L. Holton D. Alexander C. Babel H. Sutter J. Young August 2007 Prepared by the U.S. Department of Energy Office of River Protection under Contract DE-AC05-76RL01830 07-DESIGN-046 iii Summary The U.S. Department of Energy (DOE), Office of River Protection (ORP) and the DOE Office of Environmental and Radioactive Waste Management (EM), Office of Project Recovery have completed a

436

Operable Unit 3-13, Group 3, Other Surface Soils Remediation Sets 4-6 (Phase II) Waste Management Plan  

SciTech Connect

This Waste Management Plan describes waste management and waste minimization activities for Group 3, Other Surface Soils Remediation Sets 4-6 (Phase II) at the Idaho Nuclear Technology and Engineering Center located within the Idaho National Laboratory. The waste management activities described in this plan support the selected response action presented in the Final Record of Decision for Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. This plan identifies the waste streams that will be generated during implementation of the remedial action and presents plans for waste minimization, waste management strategies, and waste disposition.

G. L. Schwendiman

2006-07-01T23:59:59.000Z

437

Low-Value Waste Gases as an Energy Source  

E-Print Network (OSTI)

Waste gases with potentially useful fuel value are generated at any number of points in refineries, chemical plants and other industrial and commercial sites. The higher quality streams have been utilized successfully in fuel systems for years. Lower quality streams, often difficult to capture and sometimes limited in quantity, have often not been utilized for their fuel value. Increasing environmental and economic concerns have led to greater interest in utilizing these marginal fuel value waste gas streams as auxiliary fuels. The combustion and heat transfer characteristics of these fuels are different from normal fuels and these differences must be considered when determining if they can be fired successfully in existing furnaces or when designing new furnaces to use them. In addition, because of the difficulties in burning them and the chemical compounds that may be included in them, the potential pollutant emissions from these waste streams is also a significant consideration.

Waibel, R. T.

1996-04-01T23:59:59.000Z

438

RH-TRU Waste Inventory Characterization by AK and Proposed WIPP RH-TRU Waste Characterization Objectives  

SciTech Connect

The U.S. Department of Energy (DOE)-Carlsbad Field Office (CBFO) has developed draft documentation to present the proposed Waste Isolation Pilot Plant (WIPP) remote-handled (RH-) transuranic (TRU) waste characterization program to its regulators, the U.S. Environmental Protection Agency and the New Mexico Environment Department. Compliance with Title 40, Code of Federal Regulations, Parts 191 and 194; the WIPP Land Withdrawal Act (PL 102-579); and the WIPP Hazardous Waste Facility Permit, as well as the Certificates of Compliance for the 72-B and 10-160B Casks, requires that specific waste parameter limits be imposed on DOE sites disposing of TRU waste at WIPP. The DOE-CBFO must control the sites' compliance with the limits by specifying allowable characterization methods. As with the established WIPP contact handled TRU waste characterization program, the DOE-CBFO has proposed a Remote-Handled TRU Waste Acceptance Criteria (RH-WAC) document consolidating the requirements from various regulatory drivers and proposed allowable characterization methods. These criteria are consistent with the recommendation of a recent National Academy Sciences/National Research Council to develop an RH-TRU waste characterization approach that removes current self imposed requirements that lack a legal or safety basis. As proposed in the draft RH-WAC and other preliminary documents, the DOE-CBFO RH-TRU waste characterization program proposes the use of acceptable knowledge (AK) as the primary method for obtaining required characterization information. The use of AK involves applying knowledge of the waste in light of the materials or processes used to generate the waste. Documentation, records, or processes providing information about various attributes of a waste stream, such as chemical, physical, and radiological properties, may be used as AK and may be applied to individual waste containers either independently or in conjunction with radiography, visual examination, assay, and other sampling and analytical data. RH-TRU waste cannot be shipped to WIPP on the basis of AK alone if documentation demonstrating that all of the prescribed limits in the RH-WAC are met is not available, discrepancies exist among AK source documents describing the same waste stream and the most conservative assumptions regarding those documents indicates that a limit will not be met, or all required data are not available for a given waste stream.

Most, W. A.; Kehrman, R.; Gist, C.; Biedscheid, J.; Devarakonda, J.; Whitworth, J.

2002-02-26T23:59:59.000Z

439

Alternatives Generation and Analysis for Phase 1 High Level Waste Feed Tanks Selection  

Science Conference Proceedings (OSTI)

A recent revision of the US. Department of Energy privatization contract for the immobilization of high-level waste (HLW) at Hanford necessitates the investigation of alternative waste feed sources to meet contractual feed requirements. This analysis identifies wastes to be considered as HLW feeds and develops and conducts alternative analyses to comply with established criteria. A total of 12,426 cases involving 72 waste streams are evaluated and ranked in three cost-based alternative models. Additional programmatic criteria are assessed against leading alternative options to yield an optimum blended waste feed stream.

CRAWFORD, T.W.