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

被引：3

作者：

Itoh, Hiroto ^{[1
]}

Li, Yinsheng ^{[1
]}

Osakabe, Kazuya ^{[2
]}

Onizawa, Kunio ^{[3
]}

Yoshimura, Shinobu ^{[4
]}

机构：

[1] Japan Nucl Energy Safety Org, Minato Ku, Tokyo 1050001, Japan

[2] Mizuho Informat & Res Inst, Chiyoda Ku, Tokyo 1018443, Japan

[3] Japan Atom Energy Agcy, Tokai, Ibaraki 3191195, Japan

[4] Univ Tokyo, Bunkyo Ku, Tokyo 1138656, Japan

来源：

JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY | 2012年 / 26卷 / 07期

关键词：

Aged piping; Benchmark analysis; Probabilistic Fracture mechanics; Stress corrosion cracking;

D O I：

10.1007/s12206-012-0514-4

中图分类号：

TH [机械、仪表工业];

学科分类号：

0802 ;

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.

引用

页码：2055 / 2058

页数：4

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