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Crawford, C.L.; Farrara, D.M.; Ha, B.C.; Bibler, N.E.
Westinghouse Savannah River Company, Aiken, SC (United States). Funding organisation: USDOE, Washington, DC (United States)1998
Westinghouse Savannah River Company, Aiken, SC (United States). Funding organisation: USDOE, Washington, DC (United States)1998
AbstractAbstract
[en] The HLW glass was produced from a HLW sludge slurry (Envelope D Waste), eluate waste streams containing high levels of Cs-137 and Tc-99, solids containing both Sr-90 and transuranics (TRU), and glass-forming chemicals. The eluates and Sr-90/TRU solids were obtained from ion-exchange and precipitation pretreatments, respectively, of other Hanford supernate samples (Envelopes A, B and C Waste). The glass was vitrified by mixing the different waste streams with glass-forming chemicals in platinum/gold crucibles and heating the mixture to 1150 degree C. Resulting glass analyses indicated that the HLW glass waste form composition was close to the target composition. The targeted waste loading of Envelope D sludge solids in the HLW glass was 30.7 wt percent, exclusive of Na and Si oxides. Condensate samples from the off-gas condenser and off-gas dry-ice trap indicated that very little of the radionuclides were volatilized during vitrification. Microstructure analysis of the HLW glass using Scanning Electron Microscopy (SEM) and Energy Dispersive X-Ray Analysis (EDAX) showed what appeared to be iron spinel in the HLW glass. Further X-Ray Diffraction (XRD) analysis confirmed the presence of nickel spinel trevorite (NiFe2O4). These crystals did not degrade the leaching characteristics of the glass. The HLW glass waste form passed leach tests that included a standard 90 degree C Product Consistency Test (PCT) and a modified version of the United States Environmental Protection Agency Toxicity Characteristic Leaching Procedure (TCLP)
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Source
Sep 1998; 11 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 DE98057408; NTIS; INIS; US GOVT. PRINTING OFFICE DEP
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Report
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Conference
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Fehringer, D.J.
Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Material Safety and Safeguards1985
Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Material Safety and Safeguards1985
AbstractAbstract
[en] This report describes a possible approach for development of a numerical definition of the term ''high-level radioactive waste.'' Five wastes are identified which are recognized as being high-level wastes under current, non-numerical definitions. The constituents of these wastes are examined and the most hazardous component radionuclides are identified. This report suggests that other wastes with similar concentrations of these radionuclides could also be defined as high-level wastes. 15 refs., 9 figs., 4 tabs
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Source
Oct 1985; 36 p; Available from NTIS, PC A03/MF A01 - GPO as TI86900167
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Report
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INIS IssueINIS Issue
Bouchard, J.; Rose, B.; Sowerby, M.G.
1. Technical meeting on the nuclear transmutation of actinides. Ispra, Italy, 16-18 April 19771978
1. Technical meeting on the nuclear transmutation of actinides. Ispra, Italy, 16-18 April 19771978
AbstractAbstract
[en] Neutron physical feasibility studies have demonstrated that the hazard of the High Level Waste is reduced as function of time if minor actinides are recycled in nuclear reactors. As a consequence the potential hazard in the fuel cycle is necessarily intensified and in order to establish the magnitude of the problem the whole fuel cycle should be investigated. From the reactor point of view, it is easier to assimilate the actinides into the normal fuel cycle using a homogeneous recycling strategy. However, from the minor actinide management point of view this would demand a high degree of chemical separation so that the losses from the fuel cycle are minimized. With heterogeneous recycling more development work has to be done for reactor design, safety and operation problems. All feasibility studies in the area of neutron physics must take into account the consequences in all related fields
Primary Subject
Source
Commission of the European Communities, Ispra (Italy). Joint Research Centre; p. 437-440; 1978; p. 437-440; 1. Technical meeting on the nuclear transmutation of actinides; Ispra, Italy; 16 - 18 Apr 1977
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Report
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Conference
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Gattys, F.J.
Gattys (F.J.) Ingenieurbuero fuer Chemische Maschinen- und Apparatebau, Neu-Isenburg (Germany, F.R.)1980
Gattys (F.J.) Ingenieurbuero fuer Chemische Maschinen- und Apparatebau, Neu-Isenburg (Germany, F.R.)1980
AbstractAbstract
[en] Highly radioactive waste solutions contain nitrates (NaNO3), which are decomposed by para-formaldehyde. In order to reduce losses of formaldehyde and to accelerate the process, the waste solutions are taken via a spraying section and return flow cooler or have KHSO4 added after leaving the reaction vessel. (DG)
[de]
Die hochradioaktiven Abfalloesungen enthalten Nitrate (NaNO3), die mittels Paraformaldehyd zersetzt werden. Zur Verringerung von Verlusten an Formaldehyd und zur Beschleunigung des Verfahrens werden die Abfalloesungen nach Austritt aus dem Reaktionsgefaess ueber eine Berieselungsstrecke und Rueckflusskuehler gefuehrt bzw. KHSO4 zugesetzt. (DG)Original Title
Verfahren zur Denitration von radioaktiven Abfalloesungen
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Source
10 Jul 1980; 8 Jan 1979; 7 p; DE PATENT DOCUMENT 2900478/A/; Supplement to P 2807324.7.; ?: 8 Jan 1979
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Patent
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INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Short communication
Original Title
Stillegung und Rueckbau des WAK-Prozessgebaeudes
Primary Subject
Source
Bauer, K.G. (comp.); Deutsches Atomforum e.V., Bonn (Germany); Kerntechnische Gesellschaft e.V., Bonn (Germany); 734 p; ISSN 0720-9207;
; May 1996; p. 547-549; Inforum Verl; Bonn (Germany); Annual meeting on nuclear technology '96; Jahrestagung Kerntechnik (JK '96); Mannheim (Germany); 21-23 May 1996

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Book
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Conference
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Moore, E.L.; Calmus, D.B.
Rockwell International Corp., Richland, WA (USA). Rockwell Hanford Operations1978
Rockwell International Corp., Richland, WA (USA). Rockwell Hanford Operations1978
AbstractAbstract
[en] Preliminary acceptance criteria have been developed for packages containing nuclear waste which must be stored or disposed of by the US Department of Energy. Acceptance criteria are necessary to ensure that the waste packages are compatible with all elements of the Waste Management System. The acceptance criteria are subject to revision since many of the constraints that will be imposed on the waste packages by the Waste Management System have either not been defined or are being revised. Delineation of the acceptance criteria will provide bases for handling, transporting and disposing of the commercial waste
Primary Subject
Source
1978; 66 p; Available from NTIS., PC A04/MF A01
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Report
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Gervasio, V.; Kim, D. S.; Vienna, J. D.; Kruger, A. A.
Hanford Site (HNF), Richland, WA (United States). Funding organisation: USDOE Office of Environmental Management EM (United States)2018
Hanford Site (HNF), Richland, WA (United States). Funding organisation: USDOE Office of Environmental Management EM (United States)2018
AbstractAbstract
[en] Analyses were performed to evaluate the impacts of using the advanced glass models, constraints, and uncertainty descriptions on projected Hanford glass mass. The maximum allowable waste oxide loading (WOL) was estimated for waste compositions while simultaneously satisfying all applicable glass property and composition constraints with sufficient confidence. Different components of prediction and composition/process uncertainties were systematically included in the calculations to evaluate their impacts on glass mass. The analyses estimated the production of 23,360 MT of immobilized high-level waste (IHLW) glass when no uncertainties were taken into account. Accounting for prediction and composition/process uncertainties resulted in 5.01 relative percent increase in estimated glass mass of 24,531 MT. Roughly equal impacts were found for prediction uncertainties (2.58 RPD) and composition/process uncertainties (2.43 RPD). The immobilized low-activity waste (ILAW) mass was predicted to be 282,350 MT without uncertainty and with waste loading “line” rules in place. Accounting for prediction and composition/process uncertainties resulted in only 0.08 relative percent increase in estimated glass mass of 282,562 MT. Without application of line rules the glass mass decreases by 10.6 relative percent (252,490 MT) for the case with no uncertainties. Addition of prediction uncertainties increases glass mass by 1.32 relative percent and the addition of composition/process uncertainties increase glass mass by an additional 7.73 relative percent (9.06 relative percent increase combined). The glass mass estimate without line rules (275,359 MT) was 2.55 relative percent lower than that with the line rules (282,562 MT), after accounting for all applicable uncertainties.
Primary Subject
Source
8 Mar 2018; 133 p; OSTIID--1430075; AC05-76RL01830
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Report
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INIS IssueINIS Issue
Allen, G.C.; Luna, R.E.; Jefferson, R.M.; Wowak, W.E.
Sandia National Labs., Albuquerque, NM (USA)1983
Sandia National Labs., Albuquerque, NM (USA)1983
AbstractAbstract
[en] The Transportation Technology Center has been conducting a wide range of technical and non-technical research activities to assure the ability to transport radioactive materials in a safe, reliable, and publicly acceptable manner. These activities include tasks in Information and Intergovernmental issues, Safety Assessment and Environmental Analysis and Technology Development. Until recently, the requirements of defense waste shipments have served as a focal point for development tasks with the expectation that they would serve as a precursor for commercial activities. The passage of the Nuclear Waste Policy Act has placed additional responsibility on DOE for concerns involving the shipments of civilian materials. The development of additional research responsibilities is expected to proceed concurrently with the evolution of the transportation mission plan for civilian spent fuel and high-level wastes
Primary Subject
Source
1983; 5 p; 5. civilian radioactive waste management information meeting; Washington, DC (USA); 12-15 Dec 1983; CONF-831217--2; Available from NTIS, PC A02/MF A01 as DE84004422
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Report
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Conference
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INIS IssueINIS Issue
AbstractAbstract
[en] The PAMELA vitrification process developed by KfK is described. Information about the PAMELA plant at the Eurochemic site in Mol is presented and the exchange and handling techniques are discussed
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Journal Article
Journal
Nuclear Europe; CODEN NUEUD; v. 5(2); p. 16-17
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Eriksson, Leif G.; Dials, George E.
WM Symposia, 1628 E. Southern Avenue, Suite 9-332, Tempe, AZ 85282 (United States)2012
WM Symposia, 1628 E. Southern Avenue, Suite 9-332, Tempe, AZ 85282 (United States)2012
AbstractAbstract
[en] At the end of 2011, the world's first used/spent nuclear fuel and other long-lived high-level radioactive waste (HLW) repository is projected to open in 2020, followed by two more in 2025. The related pre-opening periods will be at least 40 years, as it also would be if USA's candidate HLW-repository is resurrected by 2013. If abandoned, a new HLW-repository site would be needed. On 26 March 1999, USA began disposing long-lived radioactive waste in a deep geological repository in salt at the Waste Isolation Pilot Plant (WIPP) site. The related pre-opening period was less than 30 years. WIPP has since been re-certified twice. It thus stands to reason the WIPP repository is the global proof of principle for safe deep geological disposal of long-lived radioactive waste. It also stands to reason that the lessons learned since 1971 at the WIPP site provide a unique, continually-updated, blueprint for how the pre-opening period for a new HLW repository could be shortened both in the USA and abroad. (authors)
Primary Subject
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2012; 17 p; WM2012: Waste Management 2012 conference on improving the future in waste management; Phoenix, AZ (United States); 26 Feb - 1 Mar 2012; Available online from: http://www.wmsym.org/archives/2012/index.html; Country of input: France; 30 refs.
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Miscellaneous
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