第5回
原子炉配管の確率論的構造健全性評価-1 溶接条件と溶接残留応力のばらつき
著者:
飛田 徹,Tohru TOBITA,勝山 仁哉,Jinya KATSUYAMA,伊藤 裕人,Hiroto ITOH,鬼沢 邦雄,Kunio ONIZAWA
発刊日:
公開日:
キーワードタグ:
Residual stress by welding would be one of the most significant factors in evaluating failure probabilities of PLR piping since the SCC growth behavior is strongly affected by residual stress distribution. The residual stress distribution is well known to ch ange caused by varying of welding conditions such as groove shape, electrical voltage and current, inter-pass temperature, etc. Therefore, to evaluate the scatter of welding condition and their influence on residual stress is important to assess the st...
英字タイトル:
Probabilistic Structural Integrity Assessment of Reactor Coolant Pressure Boundary Piping-1- The Scatter of Welding Conditions and Welding Residual Stress -
第5回
原子炉配管の確率論的構造健全性評価-2 残留応力解析による溶接条件のばらつきの影響評価
著者:
勝山 仁哉,Jinya KATSUYAMA,飛田 徹,Tohru TOBITA,伊藤 裕人,Hiroto ITOH,鬼沢 邦雄,Kunio ONIZAWA
発刊日:
公開日:
キーワードタグ:
Stress corrosion cracking (SCC) in primary loop recirculation piping made of austenitic stainless steel has been observed near welding joints. The SCC grows near the welding zone mainly due to high tensile residual stress by welding as well as the other contributing f actors of material and environment. The residual stress analysis due to welding of austenitic stainless piping is important and has been already conducted by many researchers. In present work, the effect of scatters of welding conditions such...
英字タイトル:
Probabilistic Structural Integrity Assessment of Reactor Coolant Pressure Boundary Piping-2- Residual Stress Analyses of the Effect of Scatter of Welding Conditions -
第5回
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
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:
キーワードタグ:
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 o...
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 -