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Probabilistic structural integrity analysis of reactor pressure vessels during pressurized thermal shock events

加圧熱衝撃時における原子炉圧力容器の確率論的構造健全性解析

眞崎 浩一; 勝山 仁哉; 鬼沢 邦雄

Masaki, Koichi; Katsuyama, Jinya; Onizawa, Kunio

原子炉圧力容器の加圧熱衝撃(PTS)時における構造健全性評価に関して、確率論的破壊力学(PFM)解析手法の適用性を確認するため、原子力機構ではPFM解析コードPASCAL3の開発を進めている。このPASCAL3を用いて、圧力容器の板厚,初期関連温度,溶接残留応力等のパラメータに対する感度解析を実施し、PTS時の条件付破壊確率に及ぼす影響を明確化した。また、国内の高経年原子炉圧力容器に対する標準的な解析条件を設定し、現行の評価方法に基づく決定論的な健全性解析に加えてPASCAL3による確率論的解析を実施し、両者の評価結果を比較した。この解析結果から、決定論的に求めた温度裕度と条件付き裂進展確率との間に良い相関があることを確認した。

In order to apply a probabilistic fracture mechanics (PFM) analysis to the structural integrity assessment of a reactor pressure vessel (RPV), PFM analysis code has been developed at JAEA. Using the PFM analysis code, PASCAL version 3, the conditional probabilities of crack initiation and fracture for an RPV during pressurized thermal shock events have been analyzed. Sensitivity analyses on some input parameters were performed to clarify the effect on the conditional fracture probability. Comparison between the conditional probabilities and temperature margin from current deterministic analysis method were made for some model plant conditions of domestic typical old-type RPVs. From the analyses, a good correlation between temperature margin and the conditional probability of crack initiation was obtained.

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パーセンタイル:100

分野:Engineering, Mechanical

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