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Surface Characterization of Mixed Self-Assembled Monolayers Designed for Streptavidin Immobilization
Nelson, K; Gamble, L; Jung, L; Boeckl, M; Naeemi, E; Golledge, S; Sasaki, T; Castner, D; Campbell, C; Stayton, P
Brookhaven National Lab., Upton, NY (United States); National Synchrotron Light Source (United States). Funding organisation: USDOE Office of Energy Research (ER) (United States)2001
Brookhaven National Lab., Upton, NY (United States); National Synchrotron Light Source (United States). Funding organisation: USDOE Office of Energy Research (ER) (United States)2001
AbstractAbstract
No abstract available
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AC02-98CH10886
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Journal Article
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AbstractAbstract
[en] Research in France on the solidification of high-level waste, that is, on concentrated fission product solutions, began in the late 1950s in two broad areas: the containment material itself and the solidification process. After preliminary investigation of various products, notably synthetic minerals, borosilicate glass was selected because it had two major advantages: specification tolerances compatible with some variation in the component fractions to accommodate the random chemical composition of the feed solution and relative ease of industrial-scale fabrication. Moreover, although not on a par with synthetic crystals, the glass properties show good resistance to natural environmental agents. 1 fig
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[en] The first industrial facility of vitrification started at Marcoule, last June. The principle of the continuous nuclear waste vitrification envisaged by France is briefly recalled together with both main functions of this vitrification: waste compaction and radioactivity confinement in time
[fr]
La premiere installation industrielle de vitrification a demarre a Marcoule en juin dernier. On rappelle rapidement le principe de la vitrification en continue des dechets nucleaires envisagee par la France, et les deux fonctions principales de cette vitrification: la compaction des dechets et le confinement de la radioactivite dans le tempsOriginal Title
La vitrification des dechets nucleaires
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Journal Article
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Recherche (Paris); v. 9(91); p. 698-702
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Harkey, N.H.
Savannah River Site (United States). Funding organisation: US Department of Energy (United States)2000
Savannah River Site (United States). Funding organisation: US Department of Energy (United States)2000
AbstractAbstract
[en] The purpose of this document is to provide a practical summary of the Environmental Qualification Testing Program results
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Source
6 Dec 2000; [vp.]; AC09-96SR18500; Available from PURL: https://www.osti.gov/servlets/purl/772666-GFPJRL/native/
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Report
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Gray, M.F.; Calmus, R.B.; Ramsey, G.; Lomax, J.; Allen, H.
Hanford Site, Richland, WA (United States). Funding organisation: USDOE Office of Environmental Management (United States)2010
Hanford Site, Richland, WA (United States). Funding organisation: USDOE Office of Environmental Management (United States)2010
AbstractAbstract
[en] The next generation melter (NOM) development program includes a down selection process to aid in determining the recommended vitrification technology to implement into the WTP at the first melter change-out which is scheduled for 2025. This optioneering study presents a structured value engineering process to establish and assess evaluation criteria that will be incorporated into the down selection process. This process establishes an evaluation framework that will be used progressively throughout the NGM program, and as such this interim report will be updated on a regular basis. The workshop objectives were achieved. In particular: (1) Consensus was reached with stakeholders and technology providers represented at the workshop regarding the need for a decision making process and the application of the D20 process to NGM option evaluation. (2) A framework was established for applying the decision making process to technology development and evaluation between 2010 and 2013. (3) The criteria for the initial evaluation in 2011 were refined and agreed with stakeholders and technology providers. (4) The technology providers have the guidance required to produce data/information to support the next phase of the evaluation process. In some cases it may be necessary to reflect the data/information requirements and overall approach to the evaluation of technology options against specific criteria within updated Statements of Work for 2010-2011. Access to the WTP engineering data has been identified as being very important for option development and evaluation due to the interface issues for the NGM and surrounding plant. WRPS efforts are ongoing to establish precisely data that is required and how to resolve this Issue. It is intended to apply a similarly structured decision making process to the development and evaluation of LAW NGM options.
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19 Oct 2010; 24 p; AC27-08RV14800; Also available from OSTI as DE01038044; PURL: https://www.osti.gov/servlets/purl/1038044/; doi 10.2172/1038044
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External URLExternal URL
BRANTLEY, W.M.
Duratek Technical Services, Richland, WA (United States). Funding organisation: USDOE Office of Environmental Management (EM) (United States)2004
Duratek Technical Services, Richland, WA (United States). Funding organisation: USDOE Office of Environmental Management (EM) (United States)2004
AbstractAbstract
[en] This document provides the rationale for preparing a package-specific safety document (PSSD) for the DBVS container verses developing a certified Type B package
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Source
4 Oct 2004; 40 p; DE-AC27-99RL14047; AC27-99RL14047; Available from PURL: https://www.osti.gov/servlets/purl/833517-snfPky/native/
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Report
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Bjorklund, W.J.; MacElroy, J.L.; Mendel, J.E.
Exxon Nuclear Co., Inc., Richland, WA (USA)1977
Exxon Nuclear Co., Inc., Richland, WA (USA)1977
AbstractAbstract
[en] A process is described for the vitrification of wastes containing radioactive substances. A heated bed is created of particles forming glass in a reactor, a gaseous agent is used to fluidise the bed; the waste matter containing radioactive substances in the fluidised bed is sprayed so that the metals and fission products in the waste are calcinated on the particles of the substance forming the bed and the remaining part of the waste is vaporised. The particles forming glass and the calcinated wastes are then removed from the reactor
[fr]
On decrit un procede pour la vitrification de dechets contenant des matieres radioactives, on cree un lit chauffe de particules formant du verre dans un reacteur, on assure la fluidisation du lit par un agent gazeux, on pulverise des dechets contenant des matieres radioactives dans le lit fluidise de facon que les metaux et produits de fission situes dans les dechets soient calcines sur les particules de la matiere du lit et que la partie restante des dechets soit vaporisee, et on evacue les particules formant du verre et les dechets calcines du reacteurOriginal Title
Procede de vitrification de dechets contenant des matieres radioactives
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19 Oct 1977; 10 p; FR PATENT DOCUMENT 2371046/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 10 Nov 1976, US.
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Patent
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AbstractAbstract
No abstract available
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AC02-98CH10886
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Journal Article
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INIS IssueINIS Issue
AbstractAbstract
[en] The different methods for treatment of RAW – cementation bituminization, vitrification and immobilization in ceramic matrix, as well as the requirements for matrix materials are discussed
Original Title
Матрици за имобилизиране и кондициониране на РАО
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2015; 22 p; BULATOM International Nuclear Forum. Bulgarian Nuclear Energy National, Regional and World Energy Safety; Varna (Bulgaria); 3-5 Jun 2015; Power Point Presentation
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Miscellaneous
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Conference
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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)1998
Westinghouse Savannah River Company, Aiken, SC (United States). Funding organisation: USDOE, Washington, DC (United States)1998
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)
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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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