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Le Coq, G.; Reuss, P.
Specialists meeting on resonance parameters of fertile nuclei and 239Pu. Saclay, 20-22 May 19741975
Specialists meeting on resonance parameters of fertile nuclei and 239Pu. Saclay, 20-22 May 19741975
AbstractAbstract
[en] The uncertainties on the calculation of the temperature coefficient in thermal reactors are estimated. A table gives some numerical examples of these uncertainties for 235U, 238U, 239Pu, 240Pu and 241Pu
[fr]
On donne une estimation des incertitudes sur le calcul du coefficient de temperature dans les reacteurs thermiques. Une table donne des exemples numeriques de ces incertitudes pour 235U, 238U, 239Pu et 240PuPrimary Subject
Source
Ribon, P. (ed.); European Energy Agency, 75 - Paris (France). Nuclear Data Committee; p. 291-295; Jan 1975; Specialists meeting on resonance parameters of fertile nuclei and 239Pu; Saclay, France; 20 May 1974
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AbstractAbstract
No abstract available
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ANS winter meeting; San Francisco, CA, USA; 27 Nov 1977; See CONF-771109--. Published in summary form only.
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Journal Article
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Transactions of the American Nuclear Society; v. 27 p. 923-924
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AbstractAbstract
[en] Task of optimal control of thermal reactors is considered. Solution of optimal reactor control task including process equation solvability, optimal control existence and derivation of necessary conditions of maximum principle is given. Nonlinear integral functional is selected as an optimum criterion
Original Title
Optimal'noe upravlenie yadernymi reaktorami na teplovykh nejtronakh
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Journal Article
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Zhurnal Vychislitelnoj Matematiki i Matematicheskoj Fiziki; ISSN 0044-4669; ; CODEN ZVMFA; v. 27(9); p. 1335-1348
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AbstractAbstract
[en] A panel which the IAEA had invited to attend in the Nuclear Research Centre Karlsruhe, dealt with the worldwide situation of plutonium recycling in thermal reactors. The results of the reports from the various countries concerning programmes, tendencies, questions of technology and economy are the background of the surveys and statements in this article. (orig./LN)
[de]
Die weltweite Situation der Rueckfuehrung von Plutonium in Leichtwasserreaktoren wurde kuerzlich auf einem Panel behandelt, zu dem die Internationale Atomenergie-Organisation (IAEO) in das Kernforschungszentrum Karlsruhe eingeladen hatte. Die Ergebnisse der Berichte aus den einzelnen Laendern ueber Programme, Tendenzen, Technologie und Wirtschaftlichkeitsfragen bilden den Hintergrund zu den Ueberblicken und Aussagen, die der Artikel enthaelt. (orig.)Original Title
Aspekte der Pu-Rueckfuehrung in thermische Reaktoren
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Journal Article
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Atomwirtsch., Atomtech; v. 21(1); p. 27-30
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Spronk, N.
Nuclear Activation Techniques in the Life Sciences. Proceedings of the Symposium on Nuclear Activation Techniques in the Life Sciences1967
Nuclear Activation Techniques in the Life Sciences. Proceedings of the Symposium on Nuclear Activation Techniques in the Life Sciences1967
AbstractAbstract
[en] Nuclear activation analysis of animal materials was performed as early as 1946. The materials studied were generally related in some way to human life (e.g. meat, blood, excreta) and were frequently of experimental origin (e.g. mouse, rat, rabbit or chicken). Major constituents as well as trace elements were studied, usually after activation with thermal (reactor) neutrons. Before 1962 only incidental work for biological research was performed. From then onwards a substantial increase can be noted in zoological research. The applications of nuclear activation are found in: 1. Descriptive studies: distribution of elements. 2. Experimental studies: (a) Dynamics and interaction of major and minor constituents; (b) Mineral metabolic cycle studies; (c) Radioecological studies; (d) Toxicological studies. Illustrative results in each of these sections are described. A few specific technical problems such as sampling, standardization and analysis are discussed briefly, and some of the possibilities for future research are outlined. (author)
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Source
International Atomic Energy Agency, Vienna (Austria); 726 p; Oct 1967; p. 335-350; Symposium on Nuclear Activation Techniques in the Life Sciences; Amsterdam (Netherlands); 8-12 May 1967; IAEA-SM--91/16; ISSN 0074-1884; ; 59 refs., 3 figs., 2 tabs.
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Book
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AbstractAbstract
No abstract available
Original Title
Sistema de calculo neutronico para reatores nucleares
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Anon.; Instituto de Engenharia Nuclear, Rio de Janeiro (Brazil); 240 p; 1983; p. 190; Published in summary form only.
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Miscellaneous
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Piet, Steven J.; Matthern, Gretchen E.; Jacobson, Jacob J.
Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems2007
Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems2007
AbstractAbstract
[en] Thermal recycle provides several potential benefits when used as stop-gap, mixed, or backup recycling to recycling in fast reactors. These three roles involve a mixture of thermal and fast recycling; fast reactors are required to some degree at some time. Stop-gap uses thermal reactors only until fast reactors are adequately deployed and until any thermal-recycle-only facilities have met their economic lifetime. Mixed uses thermal and fast reactors symbiotically for an extended period of time. Backup uses thermal reactors only if problems later develop in the fast reactor portion of a recycling system. Thermal recycle can also provide benefits when used as pure thermal recycling, with no intention to use fast reactors. However, long term, the pure thermal recycling approach is inadequate to meet several objectives. (authors)
Primary Subject
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American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States); 1873 p; ISBN 0-89448-055-3; ; 2007; p. 1617-1623; Advanced nuclear fuel cycles and systems (GLOBAL 2007); Boise - Idaho (United States); 9-13 Sep 2007; Country of input: France; 18 refs.
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Book
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AbstractAbstract
No abstract available
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Nov 1974; 179 p; ENDF--202
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Report
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Kukuleanu, V.; Mocioiu, D.; Drutse, E.; Konstantinesku, E.
Collection of reports on computer programs and methods of physical computations of fast reactors. CMEA1975
Collection of reports on computer programs and methods of physical computations of fast reactors. CMEA1975
AbstractAbstract
[en] The system of neutron calculation for fast reactors is given. This system was used for estimation of physical parameters of fast thermal reactors investigated. The results obtained and different specific problems of the reactors of this type are described. (author)
Original Title
Raschet nejtronnykh parametrov bysrto-teplovogo reactora
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Source
Sovet Ehkonomicheskoj Vzaimopomoshchi, Moscow (USSR). Postoyanniya Komissiya po Ispol'zovaniyu Atomnoj Ehnergii v Mirnykh Tselyakh; p. 226-249; 1975; Meeting of specialists on methods and computer programs for physical calculations of fast reactors; Dimitrovgrad, USSR; 1 Jul 1974
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Vukovic, D.
Energoprojekt, Belgrade (Yugoslavia)
Energoprojekt, Belgrade (Yugoslavia)
AbstractAbstract
No abstract available
Original Title
Analiticki model za optimalnu kontrolu prelaznih koncentracija XE135 reaktora u radu
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nd; 7 p; 19. Yugoslav Conference; Ohrid, Yugoslavia; 2 Jun 1975
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