Cognet, G.; Veteau, J.M.; Eberle, P.; Seiler, J.M.
Proceedings of fifth international topical meeting on nuclear thermal hydraulics, operations and safety1997
Proceedings of fifth international topical meeting on nuclear thermal hydraulics, operations and safety1997
AbstractAbstract
[en] In the highly unlikely event of a present PWR pressure vessel (RPV) failure, corium could fall onto the basemat of the reactor and could erode the concrete. For future reactors, it is foreseen to limit the consequences of such an event by catching and cooling the corium in a specific device named core-catcher. In particular, the EPR (European Pressurized Reactor) is considering a core-catcher concept which is based on mixing the corium with a special concrete, spreading the molten mixture on a large surface and subsequently cooling by flooding with water. Therefore, sufficient melt spreading is one of the key phenomena to achieve ex-vessel melt coolability and deserves intensive investigation. The French research programme on spreading, conducted by the CEA and its partners: EDF and FRAMATOME, is composed of three main complementary tasks: the THEMA computer code, the CORINE analytical experiments performed with low temperature simulant materials and the VULCANO global experiments carried out with 'prototypic' materials. This programme, resulting from a thorough study of possible scenarios and involved phenomena, is presented here with the latest results obtained
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Chinese Nuclear Society, BJ (China); American Nuclear Society (United States); Atomic Energy Society of Japan (Japan); American Society of Mechanical Engineers (United States); Canadian Nuclear Society (Canada); Korean Nuclear Society (Korea, Republic of); Mexican Nuclear Society (Mexico); Nuclear Society of Slovenia (Slovenia); Spanish Nuclear Society (Spain); 1493 p; 1997; p. V5.1-V5.8; 5. international topical meeting on nuclear thermal hydraulics, operations and safety; Beijing (China); 14-18 Apr 1997; Available from China Nuclear Information Centre
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Cognet, G.; Veteau, J.M.; Eberle, P.; Seiler, J.M.; Latche, J.C.
The European Pressurized Water Reactor (EPR). Proceedings1997
The European Pressurized Water Reactor (EPR). Proceedings1997
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No abstract available
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Bauer, K.G. (ed.); Kerntechnische Gesellschaft e.V., Bonn (Germany); Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris (France); 226 p; ISBN 3-926956-33-X; ; 1997; p. 223-226; Inforum Verl; Bonn (Germany); 2. international conference on the European Pressurized Water Reactor (EPR); Cologne (Germany); 19-21 Oct 1997
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