Review and categorization of existing studies on the estimation of probabilistic failure metrics for Reactor Coolant Pressure Boundary piping and steam generator tubes in Nuclear Power Plants

Wen Chi Cheng, Tatsuya Sakurahara, Sai Zhang, Pegah Farshadmanesh, Seyed Reihani, Ernie Kee, Zahra Mohaghegh, Klaus Heckmann, Jürgen Sievers, Bengt Lydell, Chokri Zammali, Xian Xun Yuan, Xinjian Duan, Robertas Alzbutas, Gyeong Geun Lee, Julia Abdul Karim, Vladimir Morozov, Cole Takasugi, Tatjana Jevremovic

Research output: Contribution to journalReview article

Abstract

This paper presents the first output of the International Atomic Energy Agency (IAEA) Coordinated Research Project (CRP), titled Methodology for Assessing Pipe Failure Rates in Advanced Water-Cooled Reactors (AWCRs), launched in 2018. This IAEA CRP is aimed at developing a good-practices document for estimating the probabilistic failure metrics of piping in AWCRs. The reliability of piping that comprise the Reactor Coolant Pressure Boundary (RCPB) is important for maintaining safe and stable operations of Nuclear Power Plants (NPPs) because failure of those piping components could lead to undesirable consequences, such as plant shutdown, costly repair, the occurrence of Loss-of-Coolant Accidents (LOCAs) and, possibly, subsequent core damage or large release events. Probabilistic failure metrics (e.g., failure rate, failure frequency, or failure probability) of RCPB components are the key inputs to the Probabilistic Safety/Risk Assessment (PSA/PRA) and risk management of NPPs. The estimation of probabilistic failure metrics, however, is challenging, especially for AWCRs, due to the lack of operating experience. Therefore, as the first step of the IAEA CRP activities, this paper is developed to provide a literature review of the existing studies (from 2000 to April 2019) on the estimation of probabilistic failure metrics for RCPB piping and Steam Generator (SG) tubes of NPPs and to categorize them based on four criteria: (1) explicitness of incorporation of physical failure mechanisms; (2) types of failure characterization; (3) types of physical models for degradation; and (4) explicitness of consideration of maintenance. The existing studies are also analyzed from the viewpoint of the following key aspects: (i) uncertainty analysis, (ii) sensitivity analysis, (iii) validation strategies, and (iv) the areas of applications.

Original languageEnglish (US)
Article number103105
JournalProgress in Nuclear Energy
Volume118
DOIs
StatePublished - Jan 2020

Keywords

  • Loss of coolant accident
  • Piping
  • Probabilistic risk assessment
  • Probabilistic safety assessment
  • Reactor Coolant Pressure Boundary
  • Steam generator tubes

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Safety, Risk, Reliability and Quality
  • Energy Engineering and Power Technology
  • Waste Management and Disposal

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    Cheng, W. C., Sakurahara, T., Zhang, S., Farshadmanesh, P., Reihani, S., Kee, E., Mohaghegh, Z., Heckmann, K., Sievers, J., Lydell, B., Zammali, C., Yuan, X. X., Duan, X., Alzbutas, R., Lee, G. G., Karim, J. A., Morozov, V., Takasugi, C., & Jevremovic, T. (2020). Review and categorization of existing studies on the estimation of probabilistic failure metrics for Reactor Coolant Pressure Boundary piping and steam generator tubes in Nuclear Power Plants. Progress in Nuclear Energy, 118, [103105]. https://doi.org/10.1016/j.pnucene.2019.103105