ASTRID Nuclear Island design : advances in French-Japanese joint team development of Decay Heat Removal systems
Résumé
ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) has the objective to integrate innovative options with the objective to prepare the 4th generation reactors.
In this framework a French-Japanese agreement was signed in 2014 between CEA, AREVA NP, JAEA, MHI/MFBR to jointly perform components design of ASTRID such as Decay Heat Removal Systems (DHRS).
In this respect an ambitious close collaboration is set in the framework of the practical elimination objective of Decay Heat Removal function loss which is one of the main ASTRID safety objectives.
To reach this target, design is driven by deterministic safety criteria, probabilistic safety indicators and proper technical and economic analysis.
Safety demonstration aims at identifying common cause failures and imposes to search for proper diversification of decay heat removal systems. In ASTRID, DHRS diversification is based on final heat sinks types, intermediate coolant fluids and spatial segregation of systems with different thermal loading during normal operation as well as severe accident exposure. Implication of two different designers bodies AREVA NP and a Japanese team (JAEA, Mitsubishi FBR Systems (MFBR) and MHI) also participate to diversification.
This paper is giving highlights of ASTRID DHRS current strategy. Focus is made on operating temperature diversification for in-vessel heat exchanger as well as core catcher coolability by an original features such as heat exchanger located within reactor cold pool, whose design was taken over by Japan team since 2014.
Origine : Fichiers produits par l'(les) auteur(s)
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