2020 Annual Meeting

Presentation information

Oral presentation

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

[1K07-12] Mitigation of Molten Core Concrete Interaction

Mon. Mar 16, 2020 3:20 PM - 4:55 PM Room K (Lecture Bildg. S 2F S-21)

Chair:Yoshiro Nishioka(TOSHIBA)

4:35 PM - 4:50 PM

[1K12] Studies on safety improvement in nuclear power plant severe accidents: enhancement of molten core coolability and mitigation of molten core concrete interaction

(6)Development of molten core spreading model

*Nobuhide Hara1, Takuo Oda1, Keisuke Yoshida1, Hironori Noguchi1, Koichi Tanimoto1, Hiroshi Goda1, Junichi Takeuchi1 (1. MHI)

Keywords:Molten Corium, CFD, MCCI, Spreading

In severe accidents, spreading length of the molten core on the floor of the container vessel is affected by viscosity change, and gas generation from the floor material. Accurate prediction of molten core spreading length is important for the safety enhancement. In this research, simulation method including viscosity change and gas generation was developed. Validation results of spreading length of VE-U7 is presented in this paper.