2022 Annual Meeting

Presentation information

Oral presentation

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

[1G01-04] Fast Reactor Safety

Wed. Mar 16, 2022 9:30 AM - 10:45 AM Room G

Chair: Kenta Murakami (UTokyo)

10:00 AM - 10:15 AM

[1G03] Studies on relocation behavior of molten core materials in the core disruptive accident of sodium-cooled fast reactors

(10)Analysis on fragmentation and cooling behavior in a limited volume sodium pool

*Hatsuki Matsushita1, Ren Kobayashi1, Takaaki Sakai1, Shinya Kato2, Ken-ichi Matsuba2, Kenji Kamiyama2 (1. Tokai Univ., 2. JAEA)

Keywords:Sodium-cooled fast reactor, Core disruptive accident, Relocation of molten core material, SIMMER-III

Analyses were carried out for sodium experiments to clarify fragmentation and cooling behavior of molten core material impinging to a horizontal structure in a sodium pool during core disruptive accident of sodium-cooled fast reactors. As a result of comparison with the experiments, it was analyzed even in the limited volume sodium condition, the simulated molten core material showed the solidification mechanism with cooling acceleration by the fragmentation after the impinging to the plate.