2021 Fall Meeting

Presentation information

Oral presentation

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

[2E15-20] SMR, Accident Evaluation Models & Power Distribution Estimation

Thu. Sep 9, 2021 4:10 PM - 5:50 PM Room E

chair: Yoshiro Nishioka (Toshiba ESS)

4:55 PM - 5:10 PM

[2E18] Modeling an interface system LOCA in the severe accident analysis code “ MAAP”

*Takayoshi Kusunoki1, Takaki Toshiya1 (1. INSS)

Keywords:severe accident, modeling, interface system LOCA

From a consideration of progression of the 2011 Fukushima Daiichi Nuclear Power Station, apparatuses introduced as power station emergency safety measures and severe accident measures in power stations were incorporated into the MAAP plant model. In this paper, in order to respond quickly to various accident sequences using the Incident Progress Prediction System, we examined the initiating events that should be modeled in advance based on the initiating events described in the safety improvement analysis reports. As a result, the ISLOCA (interface system LOCA) was extracted and modeled. We verified the operation of the model based on "Effectiveness evaluation of measures against serious accidents of Takahama No. 3 and No. 4 reactors" and found that after the event occurred the primary coolant pressure and the primary coolant temperature tended to be higher than the effectiveness evaluation after about 1 hour. The plant behavior showed a similar trend to that of the data.