現行の原子炉圧力容器の健全性評価手法に対するPASCAL3 を用いた破壊力学評価
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概要
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The probabilistic fracture mechanics analysis code PASCAL3 has been developed at JAEA to support the validation of the codes and standards that provide the structural integrity assessment method for reactor pressure vessels (RPVs) during pressurized thermal shock. The previous version of PASCAL2 has many functions including the evaluation method for an embedded crack, the PTS transient database, nondestructive inspection models. This code has been improved mainly focusing on the cladding on the inner surface of RPV. Using PASCAL3, the effects of the initiation and growth model for a surface flaw have been analyzed to determine the standard condition of PASCAL3. Deterministic and probabilistic evaluations using PASCAL3 for a current structural integrity assessment method for RPV have also been conducted. The results show that the consideration of the warm prestress effect decreases the conditional probability of failure by less than one-tenth.
著者
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西川 弘之
みずほ情報総研(株)
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勝山 仁哉
(株)日本原子力研究開発機構 安全研究センター
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鬼沢 邦雄
(株)日本原子力研究開発機構 安全研究センター
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眞崎 浩一
(株)日本原子力研究開発機構 安全研究センター