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

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Abstract

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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Authors and Affiliations

  1. Japan Nuclear Energy Safety Organization, 4-1-28 Toranomon, Minato-ku, Tokyo, 105-0001, Japan

    Hiroto Itoh & Yinsheng Li

  2. Mizuho Information & Research Institute, Chiyoda-ku, Tokyo, 101-8443, Japan

    Kazuya Osakabe

  3. Japan Atomic Energy Agency, Tokai, Ibaraki, 319-1195, Japan

    Kunio Onizawa

  4. The University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo, 113-8656, Japan

    Shinobu Yoshimura

Authors
  1. Hiroto Itoh
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  2. Yinsheng Li
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  3. Kazuya Osakabe
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  4. Kunio Onizawa
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  5. Shinobu Yoshimura
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Corresponding author

Correspondence to Yinsheng Li.

Additional information

Recommended by Guest Editor Dong-Ho Bae

Hiroto Itoh, received his Ph.D from Chuo University in 2000. He is a researcher in the Japan Nuclear Energy Safety Organization (JNES), Seismic Safety Division. His major subjects are structural integrity evaluation and risk assessment.

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Itoh, H., Li, Y., Osakabe, K. et al. Benchmark analysis on PFM analysis codes for aged piping of nuclear power plants. J Mech Sci Technol 26, 2055–2058 (2012). https://doi.org/10.1007/s12206-012-0514-4

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  • DOI: https://doi.org/10.1007/s12206-012-0514-4

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