Seismic loads for crack stability assessment, in a review of leak-before-break (LBB) applicability

The fitness for service of the facilities of operational nuclear power plants is secured by proper inspections and evaluations. Defects took place in components will be detected by periodical inservice inspection, and fitness for service of cracked components during an evaluation period is evaluated. Although variation exists in the conditions used for inspection or evaluation, it is difficult to grasp about those influences on the reliability of cracked components by the deterministic evaluation like Fitness-for-Service Codes. In this study, influences of inspection parameters (defect sizing error, percentage of defect oversight, detectable defect size, successive tests) and an evaluation parameter (crack growth rate) on failure probability were evaluated for primary loop recirculation system piping of boiling water reactors in which many stress corrosion cracks took place. From these evaluations, the dominant parameters for the reliability of piping having stress corrosion cracks were clarified, and the requirements for the inspection and evaluation for revising Fitness-for-Service Codes were proposed. 1. 緒言 2000 年の日本機械学会原子力設備規格維持規格 (1) (以下，維持規格) の発行と前後して，沸騰水型原子炉 (Boiling Water Reactor．以下，BWR)の原子炉再循環系(Primary Loop Recirculation system．以下，PLR)において応力腐食割れ(Stress Corrosion Cracking．以下，SCC)が顕在化し，既に 100 以上の SCC き裂が検出されている (2) ．供

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Seismic loads for crack stability assessment, in a review of leak-before-break (LBB) applicability

Cited by 3 publications

References 19 publications

Comparison of safety margin in LBB design of nuclear pipes based on various types of fracture resistance test specimens

Comparison of safety margin in LBB design of nuclear pipes based on various types of fracture resistance test specimens

Probabilistic leak-before-break analysis with correlated input parameters

Influence of Non-Destructive Examination Performance on Reliability of Pipes Having Stress Corrosion Cracks

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