Presentation Information

[3K07]Development of Integrated Severe Accident Analysis Code fof Sodium-cooled Fast Reactors(2)Outline of In-vessel Analysis Method and its Preliminary Application to Reactor Scale Analysis

*Hiroki Sonoda1, Satoshi Fujita1, Masaaki Inoue1 (1. NRA)

Keywords:

Sodium-cooled Fast Reactors,Severe Accident,FP transfer behavior,Analysis Code

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