Assessment of seismic fragility using a three-dimensional structural model of a reactor building

建屋3次元詳細モデルを用いた地震フラジリティ評価

西田 明美  ; 崔 炳賢  ; 塩見 忠彦; 川田 学; Li, Y. 

Nishida, Akemi; Choi, B.; Shiomi, Tadahiko; Kawata, Manabu; Li, Y.

新規制基準では地震等の外部事象評価の厳格化が求められるとともに、安全性向上評価に関する運用ガイドでは評価方法として確率論的リスク評価が挙げられている。地震を起因とした確率論的リスク評価(地震PRA)においては、建屋や配管等の応答や損傷確率(フラジリティ)のより現実的な評価が重要な課題となっている。以上の背景から、われわれは、耐震安全上重要な建屋や配管等を対象に、現実的応答解析手法やフラジリティ評価手法等の整備に取り組んでいる。本研究では、設計を超える地震動を入力として、建屋3次元詳細モデルを用いた地震応答解析を実施し、建屋の3次元挙動を考慮することで耐震安全上重要な配管等の設備にかかわる注目部位のフラジリティを評価した。本論文では、地震応答解析を通して得られた建屋の局部応答や詳細な損傷過程及びフラジリティの検討結果について報告する。

The new regulatory requirements in Japan have strengthened the mitigation of damage caused by natural disasters, such as earthquakes, and the operational guide for safety improvement evaluation recommends the probabilistic risk assessment (PRA) as the evaluation method in Japan. In the PRA of an earthquake, also known as the seismic PRA, the realistic assessment of the structural seismic response and the damage probability (fragility) assessment using the realistic response assessment of the nuclear buildings and equipment is one of the most important issues. Accordingly, the authors have conducted this study on the realistic seismic response analysis methods and seismic fragility assessment methods to ensure the seismic safety of the nuclear buildings and equipment. In this study, a nonlinear seismic response analysis is conducted for input ground motions beyond the ground motions assumed in the design by using a three-dimensional (3D) structural model of a reactor building. In addition, the damage mode of the structural components of the reactor building associated with the equipment is identified, and the seismic fragility is assessed based on the 3D behavior of the reactor building. The local response and detailed damage process of the reactor building that have been obtained through seismic response analysis, are reported in this study, along with the results of the seismic fragility assessment.