Benchmark analysis on PFM analysis codes for aged piping of nuclear power plants

被引:0
|
作者
Hiroto Itoh
Yinsheng Li
Kazuya Osakabe
Kunio Onizawa
Shinobu Yoshimura
机构
[1] Japan Nuclear Energy Safety Organization,
[2] Mizuho Information & Research Institute,undefined
[3] Japan Atomic Energy Agency,undefined
[4] The University of Tokyo,undefined
关键词
Aged piping; Benchmark analysis; Probabilistic fracture mechanics; Stress corrosion cracking;
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学科分类号
摘要
Probabilistic fracture mechanics is a rational methodology in structural reliability evaluation and risk assessment for aged piping in nuclear power plants. Several probabilistic fracture mechanical analysis codes have been improved or developed in Japan. To verify the reliability and applicability of two of these codes, we did a benchmark analysis using their basic functions in consideration of representative piping systems in nuclear power plants and typical aging mechanisms. Based on the analysis results, we concluded that the analysis results of these two codes are in good agreement.
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页码:2055 / 2058
页数:3
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