A review of probabilistic structural integrity assessment in the nuclear sector and possible future directions

There always exists uncertainty and variability in structural integrity assessments arising from lack of knowledge, modeling approximations, or differences between as‐manufactured components and as‐operated components. This may ultimately impact on reactor lives. Such uncertainties and variabilities...

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Bibliographic Details
Published in:Fatigue & fracture of engineering materials & structures 2021-12, Vol.44 (12), p.3227-3257
Main Authors: Chavoshi, Saeed Zare, Booker, Julian, Bradford, Rick, Martin, Michael
Format: Article
Language:English
Subjects:
Acceptance criteria
Damage assessment
failure
Failure analysis
Failure modes
nuclear reactor
Nuclear reactors
probabilistic assessment
Reliability analysis
Reliability engineering
Sensitivity analysis
Statistical analysis
Structural integrity
Structural reliability
Uncertainty
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Summary:There always exists uncertainty and variability in structural integrity assessments arising from lack of knowledge, modeling approximations, or differences between as‐manufactured components and as‐operated components. This may ultimately impact on reactor lives. Such uncertainties and variabilities can be understood and quantified using probabilistic techniques together with reliability‐based acceptance criteria, facilitating the quantification and management of risk. This review article provides a systematic appraisal of the latest worldwide literature and also unpublished reports from EDF UK nuclear plants, giving an overview of the existing knowledge of probabilistic/reliability structural integrity methodologies and tools from a multifaceted stance, including failure modes, problem types, material types, employed codes, correlations, and probability distributions. Structural reliability analysis at different levels is discussed, and pertinent issues on convergence testing, required number of trails, sensitivity analysis, verification of individual analyses, extremely small probabilities, reactor‐wide failure probabilities, and digital twin structural integrity monitoring are elaborated. Highlights Probabilistic methodologies are reviewed and summarized. Existing applied probabilistic analyses in the nuclear sector are reviewed. A novel Reference Damage model is presented as a candidate for design code implementation. Potential future directions are identified.
ISSN:8756-758X
1460-2695
DOI:10.1111/ffe.13572