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AbstractAbstract
[en] Special construction of a pressure-vessel for liquid metal cooled reactors, or for simulating the technical aspects of those arrangements. (J.K.)
Original Title
Druckgefaess fuer vorzugsweise fluessigmetallgekuehlte Atomkernreaktoren
Primary Subject
Source
15 Aug 1975; 3 p; AT PATENT DOCUMENT 329693/B/; Available from the Oesterreichisches Patentamt, Kohlmarkt 8-10, A-1010 Vienna, Austria
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Patent
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AbstractAbstract
No abstract available
Original Title
Patent
Primary Subject
Source
4 Feb 1975; 2 p; US PATENT DOCUMENT 3,864,210
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Patent
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AbstractAbstract
[en] In this article availability information contained within the Centralized Reliability Data Organization (CREDO) liquid-metal reactor (LMR) data base is presented, and the availability critical items lists are developed. Individual components are ranked in prioritized lists from worst to best performers from an availability standpoint. Availability, as used here, is assumed to be an inherent characteristic of the component and is not necessarily assumed to be related to plant operability
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Journal Article
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Brandstetter, Robert.
CEA, 75 - Paris (France)1971
CEA, 75 - Paris (France)1971
AbstractAbstract
No abstract available
Original Title
Procede pour la realisation d'un assemblage structurel de reacteur et reacteur realise par mise en oeuvre de ce procede
Primary Subject
Source
09 Feb 1971; 14 p; FR PATENT DOCUMENT 2124140/A/
Record Type
Patent
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Malaval, C.
Novatome Industries, 92 - Le Plessis-Robinson (France)1983
Novatome Industries, 92 - Le Plessis-Robinson (France)1983
AbstractAbstract
[en] The roof slab has a metallic annular envelope made of two shell rings and two plates filled with concrete. Cylindrical spaces are provided in the slab for the passage of the reactor components. A truncated shell ring is welded to the metallic envelope and constitutes the reinforcement element of this envelope. One shell ring separates the inner volume of the envelope in two parts; it is design with apertures to allow the passage of the reactor components. The invention can be applied more particularly to fast reactors cooled by liquid sodium
[fr]
L'invention concerne une dalle de fermeture annulaire de la cuve d'un reacteur nucleaire a neutrons rapides. Cette dalle comporte une enveloppe metallique annulaire constituee par deux viroles et deux semelles remplie de beton. Des espaces cylindriques sont menages dans la dalle pour le passage des composants du reacteur. Une virole tronconique est soudee a l'enveloppe metallique et constitue l'element de raidissement de cette enveloppe. Une virole separe le volume interne de l'enveloppe en deux parties; elle est percee d'ouvertures pour le passage des composants du reacteur. L'invention s'applique en particulier aux reacteurs nucleaires a neutrons rapides refroidis par du sodium liquideOriginal Title
Dalle de fermeture annulaire de la cuve d'un reacteur nucleaire a neutrons rapides
Primary Subject
Source
14 Oct 1983; 8 Apr 1982; 12 p; FR PATENT DOCUMENT 2525016/A/; FR PATENT APPLICATION 8206125; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 8 Apr 1982
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Patent
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AbstractAbstract
[en] The reactor concepts addressed in this section are the SSTAR and STAR-LM small lead cooled reactors without on-site refuelling, developed in the Argonne National Laboratory and other national laboratories of the USA. Detailed descriptions of these concepts are presented; short summaries of the concepts are given. The inherent safety features and passive safety design options of the STAR-LM are similar to those of the SSTAR. Because it would be redundant to list them, they are not reproduced below; the reader is referred to the sections on SSTAR
Primary Subject
Source
International Atomic Energy Agency, Division of Nuclear Power, Vienna (Austria); 274 p; ISBN 978-92-0-104209-5;
; Jun 2009; p. 228-245; ISSN 1995-7807;
; Also available on-line: http://www-pub.iaea.org/MTCD/publications/PDF/Pub1399_web.pdf; For availability on CD-ROM, please contact IAEA, Sales and Promotion Unit: E-mail: sales.publications@iaea.org; Web site: http://www-pub.iaea.org/MTCD/publications/publications.asp; 6 refs, 2 figs, 9 tabs


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Book
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Eckert, S.; Buchenau, D.; Gerbeth, G.; Stefani, F.; Weiss, F.-P.
International conference on fast reactors and related fuel cycles (FR09): Challenges and opportunities. CN-176 presentations2009
International conference on fast reactors and related fuel cycles (FR09): Challenges and opportunities. CN-176 presentations2009
AbstractAbstract
No abstract available
Primary Subject
Source
International Atomic Energy Agency, Division of Nuclear Power and Division of Nuclear Fuel Cycle and Waste Technology, Vienna (Austria); Japan Atomic Energy Agency, Ibaraki Prefecture (Tokaimura) (Japan); Japan Atomic Energy Commission, Tokyo (Japan); Ministry of Economy, Trade and Industry (Japan); Ministry of Education, Culture, Sports, Science and Technology (Japan); Japan Atomic Industrial Forum, Inc. (Japan); Wakasa Wan Energy Research Centre (Japan); Atomic Energy Society of Japan (Japan); European Nuclear Society, Brussels (Belgium); Institute of Electrical Engineers of Japan (Japan); Japan Society of Mechanical Engineers (Japan); Korean Nuclear Society, Daejeon (Korea, Republic of); European Commission, Brussels (Belgium); OECD Nuclear Energy Agency, Issy-les-Moulineaux (France); vp; 2009; [26 p.]; International conference on fast reactors and related fuel cycles (FR09): Challenges and opportunities; Kyoto (Japan); 7-11 Dec 2009; IAEA-CN--176/02-03; Also available on-line: http://www-pub.iaea.org/MTCD/Meetings/cn176_Presentations.asp; Published as PowerPoint presentation only
Record Type
Report
Literature Type
Conference
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AbstractAbstract
No abstract available
Original Title
Generateur de vapeur
Primary Subject
Source
08 Aug 1972; 13 p; FR PATENT DOCUMENT 2149983/D/; Available from INPI, Paris; Available from Institut National de la Propriete Industrielle, Paris (France) Priority claim 9 Aug 1971.
Record Type
Patent
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Radchenko, R.V.; Mokrushin, S.A.
AN SSSR. Otdel Fiziko-Tekhnicheskikh Problem Ehnergetiki Uralskogo Filiala1971
AN SSSR. Otdel Fiziko-Tekhnicheskikh Problem Ehnergetiki Uralskogo Filiala1971
AbstractAbstract
No abstract available
Original Title
Pompe electromagnetique pour le pompage de metaux liquides
Primary Subject
Source
10 Aug 1971; 7 p; FR PATENT DOCUMENT 2148935/D/; Available from INPI, Paris; Available from Institut National de la Propriete Industrielle, Paris (France).
Record Type
Patent
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AbstractAbstract
[en] The need for power reactors operating on a closed fuel cycle is very broadly discussed in the article. A brief summary of the issues and economics is provided. The article focuses on safety issues related to nuclear catastrophes at power plants. Lead-cooled fast reactors are briefly described and proposed as a solution to plutonium waste and safety issues
Primary Subject
Source
Translated from Atomnaya Energiya; 76: No. 4, 345-348(Apr 1994).
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Journal Article
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Translation
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