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Enhancing Nuclear Safety
ICAPP05, Séoul, COREE, 15-19 May 05
M. Cranga, R. Fabianelli, F. Jacq, M. Barrachin, F. Duval.
Document type >
safety, ASTEC code, corium, MEDICIS (code), molten corium concrete interaction (MCCI), severe accident
Research Unit >
BARRACHIN Marc, CRANGA Michel, DUVAL Fabien, JACQ François
Publication Date >
The MCCI code MEDICIS implemented in the reactor accident code system ASTEC-V1 addresses the ex-vessel corium long term behaviour during a severe nuclear reactor accident. The module general features are the lumped parameter approach based on a layer averaged description, the tool flexibility permitting an easy addition of new models. MEDICIS is interfaced with the thermochemistry code GEMINI2 for evaluating the molten fraction versus temperature and the composition of phases present in the melt. Due to existing large uncertainties on solidification models, the pool/crust interface temperature (solidification temperature) is evaluated from thermochemical data using an user’s input parameter to interpolate between solidus and liquidus temperatures. Consequently all situations from a complete liquid melt pool to a mushy pool with a significant solid fraction can be addressed. Main heat transfer phenomena at the pool interfaces and between layers are described. A brief overview of MEDICIS validation against some 1D experiments ACE is then presented. Finally some applications to reactor cases are documented to point out the impact of main model uncertainties in safety studies.
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