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Seiler, J.M.; Azarian, G.; Gandrille, P.; Dumontet, A.; Dutheillet; Grange, J.L.; Duriez; Goldstein, G.; Spindler, B.; Cranga, M.; Cognet, G.; Froment, K.; Gatt, J.M.; Humbert, J.M.; Laporte, T.; Richard, P.; Robert, G.; Szabo, I.; Tourasse, M.; Valin, F.; Dufour, P.
Proceedings of the OECD workshop on ex-vessel debris coolability2000
Proceedings of the OECD workshop on ex-vessel debris coolability2000
AbstractAbstract
[en] The GAREC group has performed an analysis of Ex-Vessel Corium Recovery capability for some actual and future PWR designs. This analysis includes : scenario analyses for core meltdown and corium transfer to the lower head, corium behaviour in the lower head (debris and corium pools), vessel failure, risk of vapour explosion, corium-concrete interaction and coolability, corium spreading, corium accumulation, corium-ceramic interaction, residual power distribution, long term stabilisation. This analysis is based on available and most recent experimental results (ACE, MACE, VULCANO, CIRMAT, PHYTHER, etc.), on advanced calculation tools (TOLBIAC, THEMA, CORAN, CASTEM) and on engineer evaluations. Coolability during MCCI cannot be demonstrated with the present state of scientific knowledge even if there is a great potential that it can be achieved. The paper outlines the specific aspects of the approach developed by GAREC. These aspects are based on a better knowledge of the behaviour of the corium melt. This analysis leads to the conclusion that the liquid melt in a corium pool may have rather low viscosity which in turn favours melt ejection in presence of a floating crust. The R and D program engaged by CEA in France on this subject will be outlined. For the EPR concept, the main uncertainties are related to (1)- the melt-through of the gate, (2)- the effects of late water injections. The progress performed on the spreading problem (THEMA, VULCANO) are summarised. The efforts made in support of the comprehension of corium-ceramic interactions are described. These efforts involve: basic understanding of corium-ceramic interaction, model developments, CIRMAT tests, Test for the analysis of effect related to oxygen diffusion through a metal layer. It is concluded that the attack of the ceramic may be stabilised provided that the heat extracted from below the ceramic is sufficient. Some aspects concerning consequences of vapour explosion in the reactor pit are also outlined. (orig.)
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Alsmeyer, H. (ed.); Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Kern- und Energietechnik; Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung; 593 p; ISSN 0947-8620;
; May 2000; p. 489-497; OECD Workshop on ex-vessel debris coolability; Karlsruhe (Germany); 15-18 Nov 1999; Available from TIB Hannover: ZA 5141(6475); 23 refs.

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