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Le Duigou, Y.
Commission of the European Communities, Luxembourg (Luxembourg)1990
Commission of the European Communities, Luxembourg (Luxembourg)1990
AbstractAbstract
[en] A new EC plutonium reference material is made available in the form of 5g samples of plutonium dioxide powder. Before weighing the material must be calcined at 1 2500C for two hours. The plutonium content (880.26 ± 0.44) g.kg-1 has been derived from plutonium measurements performed by three different laboratories each applying a different oxydo-reductive method. The results of the plutonium measurement, the statistical evaluation of the uncertainty of the plutonium content together with information on the impurities present in the material are given in the report
Primary Subject
Source
1990; 35 p
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Report
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Scott, Bobby R.; Hoover, Mark D.; Cheng, Yung-Sung; Schollnberger, Helmut
Lovelace Respiratory Research Institute, Albuquerque, NM (United States). Funding organisation: USDOE Office of Environmental Management (EM) (United States)2000
Lovelace Respiratory Research Institute, Albuquerque, NM (United States). Funding organisation: USDOE Office of Environmental Management (EM) (United States)2000
AbstractAbstract
[en] The main objective of this research is to evaluate health-risk distributions for plutonium (Pu) inhalation-exposure scenarios relevant to environmental management of plutonium dioxide (PuO2)-contaminated sites. These distributions incorporate variability/uncertainty
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1 Jun 2000; [vp.]; FG07-97ER62511; Available from PURL: https://www.osti.gov/servlets/purl/828385-K8FO9t/native/
Record Type
Report
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INIS IssueINIS Issue
Oshima, H.; Kubo, M.
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials. Proceedings. Volume 11983
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials. Proceedings. Volume 11983
AbstractAbstract
[en] The packaging has been developed as a packaging for plutonium oxide to be recovered from light water reactor spent fuel and is designed for easy handling within a facility. As deformation and shock absorption data for balsa wood, the data obtained from various experiments carried out when developing the packaging were used. With this packaging, it is possible to transport almost all kinds of raw powder materials required to produce fuel as stated under Section 2 not only in the country but also from abroad. The packaging is expected to be frequently used in transporting plutonium oxide powder from England and/or France which are commissioned by domestic power companies to reprocess spent fuel and also in transporting highly enriched uranium oxide which is required at FBR experimental reactors. 14 references, 5 figures, 4 tables
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Oak Ridge National Lab., TN (USA); p. 390-398; Dec 1983; p. 390-398; 7. international symposium on packaging and transportation of radioactive materials; New Orleans, LA (USA); 15-20 May 1983; Available from NTIS, PC A99/MF A01; 1 as TI84006239
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Arnal, T.; Auchapt, P.; Ferlay, A.; Marchal, P.
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials1983
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials1983
AbstractAbstract
No abstract available
Primary Subject
Source
Oak Ridge National Lab., TN (USA); p. D.I.5-D.I.6; 1983; p. D.I.5-D.I.6; 7. international symposium on packaging and transportation of radioactive materials; New Orleans, LA (USA); 15-20 May 1983; Available from NTIS, PC A21/MF A01; 1 as DE83012390
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Oshima, H.; Kubo, M.
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials1983
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials1983
AbstractAbstract
No abstract available
Primary Subject
Source
Oak Ridge National Lab., TN (USA); p. D.I.9-D.I.10; 1983; p. D.I.9-D.I.10; 7. international symposium on packaging and transportation of radioactive materials; New Orleans, LA (USA); 15-20 May 1983; Available from NTIS, PC A21/MF A01; 1 as DE83012390
Record Type
Report
Literature Type
Conference
Report Number
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Abramczyk, G. A.; Loftin, B. M.; Nathan, S. J.; Bellamy, J. S.
Savannah River Site (SRS), Aiken, SC (United States). Funding organisation: USDOE (United States)2013
Savannah River Site (SRS), Aiken, SC (United States). Funding organisation: USDOE (United States)2013
AbstractAbstract
[en] An Addendum was written to the Model 9977 Safety Analysis Report for Packaging adding a new content consisting of DOE-STD-3013 stabilized plutonium dioxide materials to the authorized Model 9977 contents. The new Plutonium Oxide Content (PuO2) Envelope will support the Department of Energy shipment of materials between Los Alamos National Laboratory and Savannah River Site facilities. The new content extended the current content envelope boundaries for radioactive material mass and for decay heat load and required a revision to the 9977 Certificate of Compliance prior to shipment. The Addendum documented how the new contents/configurations do not compromise the safety basis presented in the 9977 SARP Revision 2. The changes from the certified package baseline and the changes to the package required to safely transport this material is discussed
Primary Subject
Source
30 Jul 2013; 10 p; PATRAM 2013: International Symposium on the Packaging and Transportation of Radioactive Materials; San Francisco, CA (United States); 18-23 Aug 2013; OSTIID--1088929; DE-AC09-08SR22470; Available from http://sti.srs.gov/fulltext/SRNL-STI-2013-00445.pdf; PURL: http://www.osti.gov/servlets/purl/1088929/
Record Type
Miscellaneous
Literature Type
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External URLExternal URL
Auchapt, P.; Arnal, T.; Ferlay, A.; Marchal, P.
CEA Etablissement de la Vallee du Rhone, 30 - Bagnols-sur-Ceze (France)1983
CEA Etablissement de la Vallee du Rhone, 30 - Bagnols-sur-Ceze (France)1983
AbstractAbstract
[en] Several studies have been undertaken in France in this area. For the program discussed here, an experimental prototype facility was set up at the CEA's Cadarache Nuclear Research Center. This unit was designed for filling and emptying large-capacity (25 kg) containers, and for connecting and disconnecting them with industrial facilities without the use of vinyl wrappers. This paper describes the facility and discusses its operating principles before presenting some of the significant results obtained during active testing
[fr]
Pour resoudre les problemes de manipulations et de confinement a long terme, plusieurs etudes ont ete engagees en France; pour l'une d'entre-elles, dont on parlera ici, un ensemble experimental prototype a ete realise au CEA-CEN Cadarache. Dans une premiere partie de cet expose, on fait une description de cette installation en indiquant les principes de fonctionnement. Dans une seconde partie, on donne quelques uns des resultats significatifs qui ont ete obtenus lors des essais actifs de cette installationOriginal Title
Etude et experimentation d'un conteneur de transport d'oxyde de plutonium
Primary Subject
Source
May 1983; 6 p; 7. International symposium on packaging and transportation of radioactive materials; New Orleans, LA (USA); 15-20 May 1983
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Report
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Conference
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Martell, C.J.; Myers, W.M.
Los Alamos Scientific Lab., N.Mex. (USA)1976
Los Alamos Scientific Lab., N.Mex. (USA)1976
AbstractAbstract
[en] Three plutonium metals whose impurity contents have been accurately determined are used to evaluate spectrographic standards. Best results are obtained when (1) highly impure samples are diluted, (2) the internal standard, cobalt, is used, (3) a linear curve is fitted to the standard data that bracket the impurity concentration, and (4) plutonium standards containing 22 impurities are used
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Source
May 1976; 22 p; Available from NTIS. $3.50.
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Report
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AbstractAbstract
No abstract available
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Source
1978 winter meeting of American Nuclear Society; Washington, DC, USA; 12 - 16 Nov 1978; CONF-7811109--; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 30 p. 597-598
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Barnes, L.D.
Allied-General Nuclear Services, Barnwell, SC (USA)1978
Allied-General Nuclear Services, Barnwell, SC (USA)1978
AbstractAbstract
[en] Design criteria and conceptual designs for PuO2 transportation are discussed
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Secondary Subject
Source
1978; 10 p; 5. symposium on packaging and transportation of radioactive materials; Las Vegas, NV, USA; 7 - 12 May 1978; CONF-780506--18; Available from NTIS., PC A02/MF A01
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Report
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