1196. 地震動の不確かさを考慮した経年配管の構造信頼性評価手法の開発

抄録

The purpose of this research is to establish a stmctural reliability evaluation method for aged nuclear components under seismic events from the viewpoint of long-term use of existing light water reactor nuclear power plants. For this purpose, we developed a piping failure probability evaluation code "PASCAL-SC" and seismic hazard evaluation code "SHEAT-FM" which is reported separately. In PASCAL-SC, aging such as SCC (Stress Corrosion Cracking) and fatigue crack extension by seismic load is considered. In this paper, a reliability evaluation procedure for aged piping under seismic events by combination of these codes is described. We evaluate the reliability of a welded joint of PLR (Primary Loop Recirculation system) piping using a BWR model plant under seismic events.