2022 Annual Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 302-1 Advanced Reactor System

[1C05-08] AI Technology

Wed. Mar 16, 2022 10:45 AM - 12:00 PM Room C

Chair: Shuhei Maruyama (JAEA)

11:15 AM - 11:30 AM

[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.