TY - JOUR
T1 - Estimation of pipe failure frequencies in the absence of operational experience data
T2 - A pilot study
AU - Heckmann, Klaus
AU - Ahn, Dong Hyun
AU - Beal, John
AU - Cheng, Wen Chi
AU - Duan, Xinjian
AU - Jevremovic, Tatjana
AU - Kee, Ernie
AU - Mohaghegh, Zahra
AU - Lydell, Bengt
AU - Reihani, Seyed
AU - Sakurahara, Tatsuya
AU - Wang, Min
N1 - Funding Information:
The authors thank Robertas Alzbutas, Blair Carroll, Julia Abdul Karim, Jovica Riznic, and Chokri Zammali from the CRP team for the fruitful discussions during the collaborative work within the CRP. The authors thank the two anonymous reviewers for their thorough analysis of the work and the detailed and constructive comments. This work was supported by the International Atomic Energy Agency [Coordinated Research Project CRP I31030]. Part of this research was supported by the German Federal Ministry of Economics and Energy [projects number RS1551, RS1584]. Part of this research was supported by the U.S. Department of Energy, Office of Science, Office of Nuclear Energy University Program (NEUP), under Award #17-12614. Any opinions, findings, conclusions, or recommendations expressed in this publication are those of the authors and do not necessarily reflect the views of the Department of Energy, Office of Nuclear Energy.
Funding Information:
This work was supported by the International Atomic Energy Agency [Coordinated Research Project CRP I31030]. Part of this research was supported by the German Federal Ministry of Economics and Energy [projects number RS1551, RS1584]. Part of this research was supported by the U.S. Department of Energy, Office of Science, Office of Nuclear Energy University Program (NEUP), under Award #17-12614. Any opinions, findings, conclusions, or recommendations expressed in this publication are those of the authors and do not necessarily reflect the views of the Department of Energy, Office of Nuclear Energy.
Publisher Copyright:
© 2022 The Author(s)
PY - 2022/11
Y1 - 2022/11
N2 - 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.
AB - 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.
KW - Advanced water cooled reactor
KW - Alloy 600/82/182
KW - Alloy 690/52/152
KW - Factor of improvement
KW - Failure frequency
KW - Probabilistic assessment
KW - Reliability and integrity management
KW - Stress corrosion cracking
UR - http://www.scopus.com/inward/record.url?scp=85139001392&partnerID=8YFLogxK
UR - https://www.mendeley.com/catalogue/5f7160dc-d963-39bc-a528-8ab9cb88ee19/
U2 - 10.1016/j.nucengdes.2022.111990
DO - 10.1016/j.nucengdes.2022.111990
M3 - Article
AN - SCOPUS:85139001392
SN - 0029-5493
VL - 398
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
M1 - 111990
ER -