Estimation of pipe failure frequencies in the absence of operational experience data: A pilot study

Klaus Heckmann, Dong Hyun Ahn, John Beal, Wen Chi Cheng, Xinjian Duan, Tatjana Jevremovic, Ernie Kee, Zahra Mohaghegh, Bengt Lydell, Seyed Reihani, Tatsuya Sakurahara, Min Wang

Research output: Contribution to journalArticlepeer-review

Abstract

Probabilistic failure metrics such as leak frequency and rupture frequency are commonly used to characterize piping reliability. The methodologies for calculating the failure metrics rely on a complex set of input parameters. Operating experience data and experimental data play an important role in informing the different input parameters. The paper describes results and conclusions of a coordinated research project to benchmark three different reliability models using a four-step procedure: reference case definition of relevance to advanced reactor designs, input parameter calibration, validation of results, and application of different methodologies upon completion of the calibration and validation steps. The reference case is a weld consisting of nickel-base alloy 152/52 and located within a primary pressure boundary of an advanced reactor. This alloy is a class of structural materials known to be highly resistant to stress corrosion cracking. Synergies between the different methods are noted and the importance of a multi-disciplinary approach to input parameter development is underscored. A key conclusion is that the three methods are equally suitable for estimating failure frequencies. In any specific application, a selection of the most practical or effective computational tool can be considered. The comparison of alternative models confirms and helps to gain confidence in the computed failure frequency estimates. The study was part of a coordinated research project organized by the International Atomic Energy Agency.

Original languageEnglish
Article number111990
JournalNuclear Engineering and Design
Volume398
Early online dateOct 2 2022
DOIs
StatePublished - Nov 2022
Externally publishedYes

Keywords

  • Advanced water cooled reactor
  • Alloy 600/82/182
  • Alloy 690/52/152
  • Factor of improvement
  • Failure frequency
  • Probabilistic assessment
  • Reliability and integrity management
  • Stress corrosion cracking

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