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Boudouresques, B.; Le Diguou, A.; Le Noc, J.P.; Couture, P.
Nuclear energy maturity. Communications of the I. European nuclear conference. Paris, 21-25 April 19751975
Nuclear energy maturity. Communications of the I. European nuclear conference. Paris, 21-25 April 19751975
AbstractAbstract
[en] Fuel development and performances of the French natural uranium-graphite-gas series (GCR) are presented. From the solid rods of G2 and G3, via the hollow, closed rod of UMo 1.1% alloy of CH2 and CH3, the CEA developed a graphite core element that was to be used in all the other reactors except Bugey 1. In the case of Bugey 1, an annular form for the uranium tube, with internal and external cooling was adopted
[fr]
On presente l'evolution des elements combustibles de la filiere uranium naturel-graphite-gaz ainsi que leurs performances. Apres le barreau plein des reacteurs G2-G3 et l'element tubulaire creux et ferme en alliage UMo 1,1% de CH2 et CH3, le CEA a mis au point un element a ame de graphite qui equipera toute la filiere excepte Bugey 1. Pour Bugey-1, on a retenu un tube d'uranium de forme annulaire refroidi interieurement et exterieurementOriginal Title
Vingt annees d'experience du cycle du combustible a uranium metallique naturel
Primary Subject
Source
Lehoulier, J.; Mantega, M. (eds.); American Nuclear Society, Hinsdale, Ill.; Societe Europeenne d'Energie Nucleaire, Petit-Lancy (Switzerland); p. 105-108; 1975; Societe Francaise de l'Energie Nucleaire; Clamart, France; 1. European nuclear conference; Paris, France; 21 Apr 1975
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Book
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AbstractAbstract
No abstract available
Original Title
Patent
Primary Subject
Source
15 Oct 1974; 4 p; US PATENT DOCUMENT 3,841,965
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Patent
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Pettinger, D.S.
Nuclear Power Group Ltd., Knutsford (UK)1977
Nuclear Power Group Ltd., Knutsford (UK)1977
AbstractAbstract
[en] The purpose of this graphite moderated core construction is the unloading of the outer support construction of the core regarding horizontal support forces, which would otherwise have to be provided against bending of individual blocks due to the effects of temperature and radiation. These blocks assembled in vertical columns have through holes for accommodating fuel or control rods or for hollow spaces for this purpose with the surrounding adjacent columns. By suitable construction of the upper and lower horizontal surfaces which form the boundary of each prismatic block, inherently mutually cancelling forces are produced. These surfaces (or at least one of them) are not made even, but have spherical indentations. The centre of the sphere lies outside the block on the far side of the opposite surface, but not on the vertical axis of symmetry of the block but to one side. By suitable choice of the sphere radius and the position of its centre point the internally cancelling forces required are produced due to the effect of gravity or the blocks above. Any partial shrinkage of individual blocks are made ineffective or prevented in this way. The vertical expansion of columns and the fuel and control channels between them remains stable in operation. (TK)
[de]
Diese Graphitmoderator-Corekonstruktion bezweckt Entlastung der aeusseren Stuetzkonstruktion des Cores von horizontalen Stuetzkraeften, wie sie gegen das Verbiegen einzelner Bloecke unter dem Einfluss von Temperatur und Strahlung sonst aufzubringen sind. Diese zu Saeulen uebereinandergeschichteten Bloecke enthalten durchgehende Bohrungen zur Aufnahme von Brennstoff oder Steuerstaeben oder bilden mit den ringsum benachbarten Saeulen geeignete Hohlraeume zum gleichen Zweck. Durch entsprechende Ausbildung der oberen und der unteren, jeden prismatischen Block begrenzenden horizontalen Flaechen werden systemimmanent sich gegenseitig aufhebende Kraefte erzeugt. Diese Flaechen - oder mindestens eine der beiden - werden nicht eben sondern als Kugelkalotten ausgefuehrt. Der Kugelmittelpunkt liegt ausserhalb des Blockes jenseits der gegenueberliegenden Flaeche, jedoch nicht auf der senkrechten Symmetrieachse des Blockes sonders seitlich von ihr. Durch geeignete Wahl des Kugelradius und der Lage des Kugelmittelpunktes entstehen unter dem Einfluss der Schwerkraft des oder der darueberliegenden Bloecke die gewuenschten sich intern aufhebenden Kraefte. Damit werden etwaeige partielle Schrumpfungen einzelner Bloecke unwirksam gemacht bzw. verhindert. Die vertikale Ausrichtung der Saeulen und der in oder zwischen ihnen gebildeten Brennstoff- und Steuerkanaele bleibt im Betrieb stabil erhalten. (TK)Original Title
Coreaufbau fuer Kernreaktoren
Primary Subject
Source
3 Feb 1977; 8 p; DE PATENT DOCUMENT 1639361/B/; Also available from Dt. Patentamt, Muenchen (FRG); 16 figs.
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Patent
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AbstractAbstract
[en] During the operating life of a nuclear power plant, the neutron bombardment of the concrete structure near the reactor vessel produces tritium as a result of the activation of trace quantities of lithium in the concrete. The tritium then migrates more deeply by means of diffusion. The goal of the tests describe in this paper is to estimate the proportions of tritiated gaseous compounds likely to be release by concrete waste after the dismantling of nuclear reactor unit. The studied samples were taken from drilled core samples of the concrete containment structure of UNGG nuclear power plants undergoing decommissioning. The experiments that were carried out on both a section of the core at room temperature and on crushed concrete up to 250 C show the following conclusions. First, the apparent release rate strongly depends on the flow of gas above the sample. Storage without renewal of the atmosphere or storage in a simple vinyl package will stop the phenomenon. Secondly, in the gas releases, tritium is only found as tritiated water vapor (HTO) and not as tritiated hydrogen (HT). Thirdly, depending on the test temperature, released tritiated water also comes from the pore water and the hydrates of the concrete crystal structure. The proportion of these two forms depends on the distance of the concrete sample from the reactor. (author)
Primary Subject
Source
Societe Francaise d'Energie Nucleaire (SFEN), 75015 Paris (France); Commissariat a l'energie atomique et aux energies alternatives (CEA), CENS Saclay, 91191 Gif sur Yvette (France); 825 p; 2012; p. 749-759; NUWCEM 2011: 1. International Symposium on Cement-Based Materials for Nuclear Wastes; Avignon (France); 11-14 Oct 2011; 12 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/
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Miscellaneous
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Dubiez, P.; Gaufreteau, P.; Pitton, J.P.
Electricite de France (EDF), 92 - Clamart (France). Direction des Etudes et Recherches1997
Electricite de France (EDF), 92 - Clamart (France). Direction des Etudes et Recherches1997
AbstractAbstract
[en] The RELIASEPR method and its support tool have been recommended to carry out the functional analysis of large systems within the framework of the design of new power units. Let us first recall the principles of the method based on the breakdown of functions into tree(s). These functions are characterised by their performance and constraints. Then the main modifications made under EDF requirement and in particular the 'viewpoints' analyses are presented. The knowledge obtained from the first studies carried out are discussed. (author)
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Jul 1997; 27 p
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Report
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AbstractAbstract
[en] The objective of this paper is the optimization of nuclear power facility with the established criteria of minimum price of kWh. Example of 200 MW GCR type power plant was analysed by using digital computers IBM-705, ZUSE-23 and ELLIOTT-803
Original Title
Oprimizacija nuklearno-energetskog postrojenja
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Source
1964; 6 p; Society for Electronics,Telecommunications, Automation, and Nuclear Engineering; Belgrade (Yugoslavia); ETAN 9. Conference; Zbornik radova 9. Konferencija ETAN-a; Bled (Yugoslavia); Jun 1964; Also available from the Institute of Nuclear Sciences VINCA; 11 refs., 4 figs.
Record Type
Miscellaneous
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AbstractAbstract
[en] This article explains the current EDF dismantling policy. This policy, as well as the production unit downrating process, is based on technical, economic and social-political considerations, which are discussed first. The author then goes more concretely into the past dismantling operations and those the EDF is currently studying or undertaking and more particularly the removal of generator number 2 at the Chinon A power plant
Original Title
L'experience de demantelement d'EDF
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Secondary Subject
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Journal Article
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Chapuis, A.M.; Chevalier, G.; Yvars, M.
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire1981
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire1981
AbstractAbstract
No abstract available
Original Title
Reduction de volume des dechets de graphite contamine, par concassage et incineration
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Source
Oct 1981; 2 p; Seminar on the management of radioactive wastes from nuclear power plants; Karlsruhe, Germany, F.R; 5 - 9 Oct 1981; Published in summary form only.
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Report
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AbstractAbstract
[en] After a historical summary of the start-up schedule of the U.N.G.G. reactors and an up-date on their current performances, the author explains why, six years after the commissioning of the last reactor, their operation still requires the carrying-out of nuclear calculations. He then goes on to examine the nature of the various studies and of the means used to carry them out by Heat Production Department. The conclusion leaves the impression that, as long as reactors of this type remain in service, these methods of calculation will have to be retained intact, perhaps in an expanded organisation which would gather the nuclear calculations for the operation of all the subsidiaries
[fr]
Apres un rappel historique de l'echeancier de demarrage des reacteurs UNGG et un point de leurs performances actuelles, l'auteur explique pourquoi six ans apres le demarrage du dernier reacteur, l'exploitation de ceux-ci necessite toujours la realisation de calculs nucleaires. Il poursuit par l'examen de la nature des differentes etudes et des moyens pour les realiser mis en oeuvre par le Service de Production Thermique. La conclusion laisse penser que, tant qu'un reacteur de ce type restera en activite, ces moyens de calculs devront etre maintenus intacts, peut-etre dans une organisation elargie qui regrouperait les calculs nucleaires d'exploitation de toutes les filieresOriginal Title
Role des calculs nucleaires dans l'exploitation des reacteurs EDF de la filiere uranium naturel-graphite gaz
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Journal Article
Journal
Revue Generale Nucleaire; ISSN 0335-5004;
; (no.2); p. 167-174

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AbstractAbstract
No abstract available
Original Title
Reacteur nucleaire; GCR type reactors
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Source
08 Dec 1972; 15 p; FR PATENT DOCUMENT 2209982/A/; Available from INPI, Paris; Available from Institut National de la Propriete Industrielle, Paris (France).
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Patent
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