2018 Fall Meeting

Presentation information

Oral presentation

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

[3P05-07] LWR Performance during Accident

Fri. Sep 7, 2018 10:35 AM - 11:25 AM Room P (E21 -E Building)

Chair:Kenji Kamiyama(JAEA)

10:35 AM - 10:50 AM

[3P05] Evaluation of Molten Core Coolability in Containment Vessel using JASMINE code

*Yuzuru Iwasawa1, Toshinori Matsumoto1, Ryuhei Kawabe1, Kohei Ajima1, Tomoyuki Sugiyama1, Yu Maruyama1 (1. JAEA)

Keywords:Severe accident, JASMINE, Agglomeration, Melt spreading

For assessment the molten core coolability during severe accident in LWRs, we improved the models in the JASMINE code regarding to agglomeration of melt particles and melt spreading in containment vessel based on the DEFOR-A and the PULiMS experiments conducted by KTH. The improved models generally show good agreement with these experimental results.