Uncertainty evaluation of seismic response of a nuclear facility using simulated input ground motions

模擬入力地震動を用いた原子力施設の地震応答解析結果の不確定性評価

崔 炳賢  ; 西田 明美  ; 村松 健*; 高田 毅士*  

Choi, B.; Nishida, Akemi; Muramatsu, Ken*; Takada, Tsuyoshi*

本稿では、モデル化手法の違いが原子力施設の地震応答解析結果のばらつきに与える影響を明らかにするため、多様な模擬入力地震動を用いた地震応答解析を実施し、応答のばらつきの統計的分析を行った。特に、建屋せん断壁の最大加速度応答に着目し、モデル化手法による応答結果への影響、応答のばらつき要因について分析を行い、得られた知見について報告する。

In order to clarify the influence of the difference of modeling method on the variation of the result of seismic response analysis of nuclear facility, seismic response analysis using various simulated input ground motions was carried out and the sensitivity analyses of the variations in seismic response was conducted. In particular, we focused on the maximum acceleration response of reactor building shear walls, the effect of modeling method on response result and the factors of response variation were described and discussed.