原子炉配管の確率論的構造健全性評価-3 溶接残留応力に関する確率論的破壊力学解析


英字タイトル:
Probabilistic Structural Integrity Assessment of Reactor Coolant Pressure Boundary Piping-3 - Probabilistic Fracture Mechanics Analyses Concerning Welding Residual Stress Distribution -
著者:
伊藤 裕人 Hiroto ITOH 勝山 仁哉 Jinya KATSUYAMA 飛田 徹 Tohru TOBITA 鬼沢 邦雄 Kunio ONIZAWA
発刊日:
公開日:
カテゴリ: 第5回
キーワードタグ:

概要

A probabilistic fracture mechanics (PFM) analysis code PASCAL-SP, which evaluates failure probabilities at welded joints in piping where being susceptible to stress corrosion cracking (SCC), h as been developed. This code is based on Monte Carlo simulation technique and Japanese code related to the SCC evaluation. Uncertainties and scatters of welding residual stress distribution we re modeled using database obtained from parametric FEM analyses. Sensitivity analyses concerning uncertainties and scatters of welding residual stress distribution by PASCAL-SP were performed. It was shown that failure probability was largely affected by uncertainties and scatters of welding residual stress distribution and increased with increasing the uncertainties and scatters.


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