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Advanced numerical simulation and safety demonstration of generation IV concepts


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Titre du congrès :ICAPP seventh International Conference on Advances in Nuclear Power Plants Ville du congrès :Nice Date du congrès :13/05/2007

Type de document > *Congrès/colloque

Mots clés > code de calcul, génération IV, réacteur GEN IV

Unité de recherche > IRSN/DSR

Auteurs > BRUNA Giovanni, COUTURIER Jean, MICAELLI Jean-Claude

Date de publication > 18/05/2007

Résumé

This paper, after stressing the current safety analysis practice for commercial reactors, investigates and discusses the new challenges facing the nuclear community in the field of advanced numerical simulation for the safety demonstration of the most attractive concepts among those selected by the Generation IV International Forum in 2002, i.e.: the High Temperature / Very High Temperature Reactors, HTR/VHTR, the Sodium Fast Reactors, SFR, and the Gas Fast Reactors, GFR. The paper widely emphasizes the new needs in terms of computation, validation and experimental qualification of computer codes and chains which show-up as a consequence of a new design and an advanced operation. All those needs engender new and quite challenging requests for well fitted experimental programs and connected R&D activities.