[2G10-13] Sodium-cooled Fast Reactor 1

3:15 PM - 3:30 PM JST(6:15 AM - 6:30 AM UTC)

[2G12] Development of Failure Mitigation Technologies for Improving Resilience of Nuclear Structures(31) Fragility Evaluation of Reactor Vessel based on Seismic Response Analysis

*Hiroyuki Nishino¹, Kenichi Kurisaka¹, Satoshi Futagami¹, Tomoyoshi Watakabe¹, Hidemasa Yamano¹ (1. JAEA)

Keywords:

Seismic response analysis,Excessive earthquake,Fragility evaluation,Buckling,Fatigue failure

In conventional seismic evaluation of reactor vessel (RV), buckling has been regarded as loss of function. This study considers that actual loss of function is caused by accumulation of fatigue damage after buckling, and this consideration in the evaluation is regarded as the measure for improving resilience of RV against excessive earthquake. Based on this, we analyzed the RV structural behavior after seismic shaking-induced buckling by using the finite element method, and we evaluated the probability of the RV buckling and fatigue failure (i.e., fragility).