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    Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard

    Source: Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 003::page 31501
    Author:
    Mano, Akihiro
    ,
    Yamaguchi, Yoshihito
    ,
    Katsuyama, Jinya
    ,
    Li, Yinsheng
    DOI: 10.1115/1.4042115
    Publisher: American Society of Mechanical Engineers (ASME)
    Abstract: Probabilistic 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.
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      Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4258777
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    contributor authorMano, Akihiro
    contributor authorYamaguchi, Yoshihito
    contributor authorKatsuyama, Jinya
    contributor authorLi, Yinsheng
    date accessioned2019-09-18T09:05:38Z
    date available2019-09-18T09:05:38Z
    date copyright5/3/2019 12:00:00 AM
    date issued2019
    identifier issn2332-8983
    identifier otherners_005_03_031501
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4258777
    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.
    publisherAmerican Society of Mechanical Engineers (ASME)
    titleImprovement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard
    typeJournal Paper
    journal volume5
    journal issue3
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4042115
    journal fristpage31501
    journal lastpage031501-8
    treeJournal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 003
    contenttypeFulltext
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    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
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