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AbstractAbstract
No abstract available
Original Title
Tornado protection
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Nov 1974; 53 p
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Report
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Reilly, D.; Augustson, R.
Los Alamos National Lab., NM (USA)1985
Los Alamos National Lab., NM (USA)1985
AbstractAbstract
[en] A physical inventory verification (PIV) was simulated at a mixed-oxide fuel fabrication facility. Safeguards inspectors from the International Atomic Energy Agency (IAEA) conducted the PIV exercise to test inspection procedures under ''realistic but relaxed'' conditions. Nondestructive assay instrumentation was used to verify the plutonium content of samples covering the range of material types from input powders to final fuel assemblies. This paper describes the activities included in the exercise and discusses the results obtained. 5 refs., 1 fig., 6 tabs
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Source
1985; 7 p; 7. symposium on safeguards and nuclear material management; Liege (Belgium); 21-23 May 1985; CONF-850556--8; Available from NTIS, PC A02/MF A01 as DE85012715
Record Type
Report
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Conference
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AbstractAbstract
[en] The report treats the feasibility of safeguarding a wide-scale domestic mixed oxide industry. It presents the results of an effort originally undertaken as part of the GESMO environmental impact statement and is being published as a technical report in order to provide information which would otherwise be unavailable due to the termination of the GESMO activity. The characteristics of a projected wide-scale MOX industry, the perceived threat to that industry, and the possible consequences of sabotage or theft of nuclear material are discussed. Safeguards strategies, technical approaches, and currently existing safeguards requirements and their applicability to safeguarding a MOX industry are discussed and their economic costs and societal impacts assessed
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May 1978; 24 p; NUREG--0414-ES; Available from NTIS. PC A02/MF A01
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Report
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
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Source
ANS annual meeting; San Diego, CA, USA; 18 Jun 1978; See CONF-780622--. Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 28 p. 369-370
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INIS IssueINIS Issue
AbstractAbstract
[en] Topics discussed are: safeguards considerations for the MOX fuel industry; approaches to safeguards; reference safeguards system;alternative safeguards options; and societal impacts
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Source
May 1978; 317 p; NUREG--0414; Available from NTIS. PC A14/MF A01
Record Type
Report
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Boston, R.A.
International training course on implementation of state systems of accounting for and control of nuclear materials: proceedings1984
International training course on implementation of state systems of accounting for and control of nuclear materials: proceedings1984
AbstractAbstract
[en] Physical inventories are taken periodically to meet Company, State and IAEA requirements. Those physical inventories may be verified by IAEA and/or State inspectors. This presentation describes in an introductory but detailed manner the approaches and procedures used in planning, preparing, conducting, reconciling and reporting physical inventories for the Model Plant. Physical inventories are taken for plant accounting purposes to provide an accurate basis for starting and closing the plant material balance. Physical inventories are also taken for safeguards purposes to provide positive assurance that the nuclear materials of concern are indeed present and accounted for
Primary Subject
Source
Los Alamos National Lab., NM (USA); Exxon Nuclear Co., Inc., Richland, WA (USA); p. 24.1-24.20; Jun 1984; p. 24.1-24.20; 4. international training course on implementation of state systems of accounting for the control of nuclear materials (SSAC); Santa Fe, NM (USA); 17 Oct - 4 Nov 1983; Available from NTIS, PC A99/MF A01; 1 as DE85004636
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Report
Literature Type
Conference
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Reference NumberReference Number
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AbstractAbstract
No abstract available
Primary Subject
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. 295
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Tokarz, F.J.; Murray, R.C.; Sorensen, H.C.
California Univ., Livermore (USA). Lawrence Livermore Lab1975
California Univ., Livermore (USA). Lawrence Livermore Lab1975
AbstractAbstract
[en] The structural integrity and possible failure modes of mixed-oxide fuel fabrication plants (MOFFP) subjected to different ground-motion intensities ranging from 0.1- to 1.0-g peak accelerations was studied. To perform this study, calculation models of safety-related systems to be used in the analysis were developed. Both elastic and inelastic dynamic response analyses for both horizontal and vertical ground motion were performed. Conclusions drawn regarding the structural integrity for the model MOFFP are as follows: (1) no structural damage at ground motions <0.4 g; (2) severe structural damage at 0.4 to 0.5 g; (3) complete building collapse at >0.5 g; and (4) building collapse before equipment failure. (U.S.)
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14 Feb 1975; 27 p
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Report
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Arslan, M.; Bariteau, J.P.; Couty, Y.; Favet, D.
The need for integral critical experiments with low-moderated MOX fuels2004
The need for integral critical experiments with low-moderated MOX fuels2004
AbstractAbstract
[en] The main industrial facilities involved in closing the back-end of the nuclear fuel cycle in France are La Hague reprocessing plants in which fission products are vitrified and recycle materials are recovered and purified, and MELOX plant where the recovered plutonium is used to fabricate MOX fuel. These facilities are operated by AREVA/COGEMA. Since the opening of the first plutonium box at the MELOX plant in February 1995, a huge return of experience has been accumulated in the operation of the first large-scale industrial and highly automated MOX manufacturing plant in the world. The results which will be presented in this paper are the consequences of the permanent quality improvement policy implemented since start-up as a necessary condition to satisfy safety requirements as well as commercial, economical and social constraints. In the first part of the paper, a detailed history of production since February 1995 up to 2003 will be presented, with special emphasis on 1997 (first year of 100 tHM production), March 1998 (a one-month demonstration period concluding with 19 t production), and since 1999 (beginning of multi-design productions within the limits of the decree). The second part of the paper will be devoted to the results and performances of the plant since start-up. Finally, the paper will present the prospects for the future, and especially in the development of the level of production up to 145 tHM within the limits of the new decree. (author)
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Organisation for Economic Co-Operation and Development - Nuclear Energy Agency, 75 - Paris (France); 219 p; ISBN 92-64-02078-0;
; 2004; p. 13-21; Workshop of the OECD/NEA Nuclear Science Committee; Paris (France); 14-15 Apr 2004

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Book
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AbstractAbstract
[en] The automated fabrication process is executed and supervised by an operational control unit. The operational control unit is programmed to dose the different powder components and to perform the single fabrication steps to obtain the powder composition desired. According to the powder specifications the amounts of the components are variable. They have to be programmed and have to comply with the requirements of criticality safety. Criticality safety is based on fixed values as content of fissile material, moderation and powder densities to assess the safety of equipment and to determine safe or subcritical masses. To maintain criticality safety independent from the variable values programmed within the operational control unit, an active safety system has been introduced which controls and limits the criticality parameters at fixed values. The general design criteria for criticality safety are given. The different fabrication steps are explained and the safety measures as applied are demonstrated. (Author)
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Source
AEA Reactor Services, Winfrith (United Kingdom); Nuclear Energy Agency, 75 - Paris (France); International Atomic Energy Agency, Vienna (Austria); British Nuclear Energy Society, London (United Kingdom); 374 p; 1991; v. 2 p. V.130-V.14; AEA Technology; Winfrith (United Kingdom); ICNC '91: international conference on nuclear criticality safety; Oxford (United Kingdom); 9-13 Sep 1991
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Book
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Conference
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