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Ferrara, D.M.; Crawford, C.L.; Ha, B.C.; Bibler, N.E.
Westinghouse Savannah River Company, Aiken, SC (United States). Funding organisation: USDOE, Washington, DC (United States)
Westinghouse Savannah River Company, Aiken, SC (United States). Funding organisation: USDOE, Washington, DC (United States)
AbstractAbstract
[en] 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)
Primary Subject
Source
Sep 1998; 12 p; SPECTRUM '98: nuclear and hazardous waste management international topical meeting; Denver, CO (United States); 13-18 Sep 1998; CONF-980905--; CONTRACT AC09-96SR18500; ALSO AVAILABLE FROM OSTI AS DE98057414; NTIS; INIS; US GOVT. PRINTING OFFICE DEP
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Report
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Conference
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Standke, S.; Heinzel, M.; Hanella, G.
Brennstoffinstitut Freiberg (German Democratic Republic)
Brennstoffinstitut Freiberg (German Democratic Republic)
AbstractAbstract
[en] The invention describes the preparation of an ISO container, so that it can be used for the transport of low-level radioactive wastes contained in drums
Original Title
ISO-Container zum Transport radioaktiver Abfaelle
Primary Subject
Secondary Subject
Source
1 Aug 1984; 2 Feb 1982; vp; DD PATENT DOCUMENT 212170/B/; Available from BUCHEXPORT, DDR-7010 Leipzig; ?: 2 Feb 1982
Record Type
Patent
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Gruhlke, J.M.; Galpin, F.L.
Proceedings of the Fifth Annual Participants' Information Meeting: DOE Low-Level Waste Management Program
Proceedings of the Fifth Annual Participants' Information Meeting: DOE Low-Level Waste Management Program
AbstractAbstract
[en] Low-level radioactive waste (LLW) includes a wide variety of waste types. Many organizations are contemplating the merits of declaring certain LLW as de minimus. The concept of de minimus has considerable support, as evidenced by the comments on NRC's rulemaking for 10 CFR Part 61, Licensing Requirements for Land Disposal of Radioactive Waste. Practical and philosophical considerations lend weight to the further investigation of the de minimus concept for LLW. The Environmental Protection Agency (EPA) recognizes the interest and efforts in the concept of de minimus. Because the term de minimus may imply a lack of concern for the risks of disposal, we use the term Below Regulatory Concern (BRC). EPA has developed technical information, cost data, and a methodology for selecting promising candidate waste streams. The NRC's breakdown of LLW, as provided in the supporting documentation for 10 CFR Part 51, serves as a starting point for evaluating individual waste streams. Waste streams may then be ranked on the basis of individual dose, population health impact, and cost/benefit. A set of waste streams consistently ranks near the top in all categories and deserves further analysis. This screening is the initial step in an overall effort to develop a basis for determining the appropriateness and form of generic BRC criteria. 14 references, 8 tables
Primary Subject
Source
EG and G Idaho, Inc., Idaho Falls (USA); p. 359-380; 1983; p. 359-380; 5. annual participants information meeting of DOE low level waste management program; Denver, CO (USA); 30 Aug - 1 Sep 1983; Available from NTIS, PC A99/MF A01 as DE84004134
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Report
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Loghry, S.L.; Kibbey, A.H.; Godbee, H.W.; Icenhour, A.S.; DePaoli, S.M.
Oak Ridge National Lab., TN (United States). Funding organisation: USDOE, Washington, DC (United States)
Oak Ridge National Lab., TN (United States). Funding organisation: USDOE, Washington, DC (United States)
AbstractAbstract
[en] This technical manual presents updated generic source terms (i.e., unitized amounts and radionuclide compositions) which have been developed for use in the Integrated Data Base (IDB) Program of the U.S. Department of Energy (DOE). These source terms were used in the IDB annual report, Integrated Data Base for 1992: Spent Fuel and Radioactive Waste Inventories, Projections, and Characteristics, DOE/RW-0006, Rev. 8, October 1992. They are useful as a basis for projecting future amounts (volume and radioactivity) of low-level radioactive waste (LLW) shipped for disposal at commercial burial grounds or sent for storage at DOE solid-waste sites. Commercial fuel cycle LLW categories include boiling-water reactor, pressurized-water reactor, fuel fabrication, and uranium hexafluoride (UF6) conversion. Commercial nonfuel cycle LLW includes institutional/industrial (I/I) waste. The LLW from DOE operations is category as uranium/thorium fission product, induced activity, tritium, alpha, and open-quotes otherclose quotes. Fuel cycle commercial LLW source terms are normalized on the basis of net electrical output [MW(e)-year], except for UF6 conversion, which is normalized on the basis of heavy metal requirement [metric tons of initial heavy metal ]. The nonfuel cycle commercial LLW source term is normalized on the basis of volume (cubic meters) and radioactivity (curies) for each subclass within the I/I category. The DOE LLW is normalized in a manner similar to that for commercial I/I waste. The revised source terms are based on the best available historical data through 1992
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Jan 1995; 87 p; CONTRACT AC05-84OR21400; Also available from OSTI as DE95006494; NTIS; US Govt. Printing Office Dep
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Report
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INIS IssueINIS Issue
Shevelan, John; Smith, Nicholas T.
The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
AbstractAbstract
[en] The UK Low Level Waste Repository Ltd (LLWR) submitted an Environmental Safety Case (ESC) for the disposal of low-level waste (LLW) to the UK Environment Agency on the 1 May 2011. As part of the ESC, the LLWR have to demonstrate that a programme of site investigation and site characterisation has been carried out to provide the requisite information for the ESC and support facility design and construction. This paper explains the development of the site investigation programme and how the understanding of the geology of the site has developed. The geological environment in the region of the LLWR consists of Quaternary age deposits overlying older bedrock. The site has been subjected to a series of site investigation programmes from 1939 to the present day. The development of 3-D geological models was necessary to integrate data from boreholes, trial pits, geophysical investigations and beach exposures and data gained from site operations. The understanding of the geology has developed with each new set of data. Early simple interpretations from a few boreholes have been superseded by a series of more complex interpretations each incorporating the increasingly detailed observations. Initial attempts to develop a litho-stratigraphic representation of the geology proved difficult. It was also difficult provide a clear link between the geology and the hydrogeology using a litho-stratigraphic approach as required for the development of hydro-geological models. A litho-facies approach to characterising the geology was adopted in 2007, which has allowed the grouping of geological units with similar hydraulic properties and the development of a regional 3-D geological model. The 3-D geological model has been used as the framework for the development of a hydro-geological model for the site. The development of the 3-D geological models has been iterative. It was observed that there are differences between models developed using solely mathematical interpolation and those controlled by geological interpretation. The different representations of the geological information have been used to consider the effects of uncertainty in the geological interpretation in the hydro-geological modelling. (authors)
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2012; 10 p; American Society of Mechanical Engineers - ASME; New York (United States); ICEM2011: 14. international conference on Environmental Remediation and Radioactive Waste Management; Reims (France); 25-29 Sep 2011; Country of input: France; 22 refs.
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Book
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Conference
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Dyer, J. A.
Savannah River Site (SRS), Aiken, SC (United States). Funding organisation: USDOE (United States)
Savannah River Site (SRS), Aiken, SC (United States). Funding organisation: USDOE (United States)
AbstractAbstract
[en] A design check will be performed on the infiltration-rate time profile for the intact case for the proposed E-Area Low-Level Waste Facility (LLWF) final closure cap design.
Primary Subject
Source
6 Jun 2018; 23 p; SRNL--L3200-2018-00066; AC09-08SR22470; Available from https://www.osti.gov/servlets/purl/1459417; DOE Accepted Manuscript full text, or the publishers Best Available Version will be available free of charge after the embargo period; DOI: 10.2172/1459417
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Report
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External URLExternal URL
AbstractAbstract
[en] During 1982, Inter/Face Associates, Inc., conducted a low-level radioactive waste management survey of Nuclear Regulatory Commission (NRC) licensees in Massachusetts for the US Department of Energy's National Low-Level Waste Management Program. In the process of conducting the survey, a model was developed, based on existing NRC license classification systems, that would identify licensees who ship low-level waste for disposal. This report presents the model and documents the procedures used in developing and testing it. After the model was tested, several modifications were developed with the goal of determining the model's ability to identify waste shippers under different parameters. The report includes a discussion of the modifications
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Source
Mar 1983; 41 p; Available from NTIS, PC A03/MF A01; 1 as DE83009469
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Report
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Gloyna, E.F.
Waste management '80, the state of waste disposal technology, mill tailings, and risk analysis models, proceedings of the symposium on waste management, 1980
Waste management '80, the state of waste disposal technology, mill tailings, and risk analysis models, proceedings of the symposium on waste management, 1980
AbstractAbstract
[en] In all waste management considerations, it is necessary to establish the waste source; characterize the waste components; determine treatability; evaluate specific details that comprise a systems approach to overall waste management; and implement practical collection, packaging, storage disposal and monitoring technology. This paper evaluates management considerations by defining the source and magnitude of low-level wastes (LLW), relating LLW disposal, defining principles of LLW burial, and listing LLW burial considerations. 17 refs
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Source
Post, R.G. (ed.); p. 9-20; 1980; p. 9-20; University of Arizona; Tucson, AZ; Waste management conference; Tucson, AZ, USA; 10 Mar 1980
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AbstractAbstract
[en] In the nineties, France introduced the concept of very low level radioactive waste because it considered that any waste from a restricted area may have a residual contamination. It is now obvious that the level of radioactivity of a large part of this waste is extremely low and presents no danger for the public. The introduction of a clearance threshold below which waste is no longer considered as dangerous, could save money and reserve storage capacity to waste whose level of radioactivity is higher than natural activity. The implementation of a clearance threshold would imply fastidious measurement campaigns because the level of radioactivity to be detected is very low and can favour deceitful attitude: radioactive waste could be mixed with non-radioactive materials until the global radioactivity level is below the clearance threshold. Some consider that the management of waste must be based on the place of origin whatever the real radioactivity level is, which is necessary to ensure the traceability. (A.C.)
Original Title
La France doit-elle instaurer un seuil de liberation?
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Journal Article
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Vijayarajan, A.E.; Sambukumaran, S.; Ahmed, Jaleel; Panicker, P.K.
National symposium on management of radioactive and toxic wastes
National symposium on management of radioactive and toxic wastes
AbstractAbstract
[en] Short communication
Primary Subject
Source
Rana, D.S.; Govindan, A.K. (Bhabha Atomic Research Centre, Bombay (India). Waste Management Projects Division) (eds.); Department of Atomic Energy, Bombay (India). Board of Research in Nuclear Sciences; [206 p.]; 1995; p. 152; Bhabha Atomic Research Centre; Bombay (India); SMART-95: national symposium on management of radioactive and toxic wastes; Bombay (India); 20-21 Mar 1995
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