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Enhancing Nuclear Safety


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Advanced numerical simulation and safety demonstration of generation IV concepts


Congress title :ICAPP seventh International Conference on Advances in Nuclear Power Plants
Congress location :Nice
Congress date :13/05/2007

Document type > *Congrès/colloque

Keywords > computer code, GEN IV reactor, generation IV

Research Unit > IRSN/DSR

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

Publication Date > 18/05/2007

Summary

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.
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