Presentation Information

11:15 AM - 11:30 AM JST(2:15 AM - 2:30 AM UTC)

[1C07]Development of Advanced Reactor Knowledge- and AI-aided Design Integration Approach through the whole plant lifecycle, ARKADIA(6)Development of ex-vessel analysis model in ARKADIA-Safety for safety evaluation

*Akihiro Uchibori¹, Mitsuhiro Aoyagi¹, Masateru Sonehara¹, Joji Sogabe¹, Yasushi Okano¹, Takashi Takata² (1. JAEA, 2. UTokyo)

Keywords:

Innovative nuclear reactor,Sodium-cooled fast reactor,Safety evaluation,Severe accident,Ex-vessel phenomena

ARKADIA-Safety has been developed as a safety evaluation system for innovative nuclear reactors. This paper presents validation of sodium fire analsysis model and integration of ex-vessel analysis model.

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