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dc.contributor.authorMano, Akihiro
dc.contributor.authorYamaguchi, Yoshihito
dc.contributor.authorKatsuyama, Jinya
dc.contributor.authorLi, Yinsheng
dc.date.accessioned2019-09-18T09:05:38Z
dc.date.available2019-09-18T09:05:38Z
dc.date.copyright5/3/2019 12:00:00 AM
dc.date.issued2019
dc.identifier.issn2332-8983
dc.identifier.otherners_005_03_031501
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4258777
dc.description.abstractProbabilistic fracture mechanics (PFM) analysis is expected to be a rational method for structural integrity assessment because it can consider the uncertainties of various influence factors and evaluate the quantitative values such as failure probability of a cracked component as the solution. In the Japan Atomic Energy Agency, a PFM analysis code PASCAL-SP has been developed for structural integrity assessment of piping welds in nuclear power plants (NPP). In the past few decades, a number of cracks due to primary water stress corrosion cracking (PWSCC) have been detected in nickel-based alloy welds in the primary piping of pressurized water reactors (PWRs). Thus, structural integrity assessments considering PWSCC have become important. In this study, PASCAL-SP was improved considering PWSCC by introducing several analytical functions such as the models for evaluation of crack initiation time, crack growth rate (CGR), and probability of crack detection. By using the improved version of PASCAL-SP, the failure probabilities of pipes with a circumferential crack or an axial crack due to PWSCC were numerically evaluated. Moreover, the influence of leak detection and nondestructive examination (NDE) on failure probabilities was detected. Based on the obtained numerical results, it was concluded that the improved version of PASCAL-SP is useful for evaluating the failure probability of a pipe considering PWSCC.
dc.publisherAmerican Society of Mechanical Engineers (ASME)
dc.titleImprovement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard
dc.typeJournal Paper
dc.journal.volume5
dc.journal.issue3
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4042115
dc.journal.fristpage31501
dc.journal.lastpage031501-8
dc.treeJournal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 003
dc.contenttypeFulltext


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