2020 Annual Meeting

Presentation information

Oral presentation

IV. Nuclear Plant Technologies » 402-1 Nuclear Safety Engineering (Safety Design, Safety Assessment/Analysis, Management)

[1K05-06] Numerical analysis of Molten Corium Behavior

Mon. Mar 16, 2020 2:45 PM - 3:20 PM Room K (Lecture Bildg. S 2F S-21)

Chair:Kenji Kamiyama(JAEA)

2:45 PM - 3:00 PM

[1K05] Validation and Verification for the multi-physics models in JUPITER code

*Penghui Chai1, Susumu Yamashita1 (1. Japan Atomic Energy Agency)

Keywords:JUPITER code, Severe Accident, multi-physics models, code validation

Various numerical simulations were performed by JUPITER code in order to validate the reliability of its multi-physics models, which were developed for evaluating the melting and relocation behavior of the core materials. By comparing with the previous experimental results, we could conclude that JUPITER code is a useful tool on severe accident analysis.