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    Life Prediction and Monitoring of Nuclear Power Plant Components for Service-Related Degradation

    Source: Journal of Pressure Vessel Technology:;2001:;volume( 123 ):;issue: 001::page 58
    Author:
    Fredric A. Simonen
    ,
    Stephen R. Gosselin
    DOI: 10.1115/1.1344237
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper describes industry programs to manage structural degradation and to justify continued operation of nuclear components when unexpected degradation has been encountered due to design materials and/or operational problems. Other issues have been related to operation of components beyond their original design life in cases where there is no evidence of fatigue crack initiation or other forms of structural degradation. Data from plant operating experience have been applied in combination with inservice inspections and degradation management programs to ensure that the degradation mechanisms do not adversely impact plant safety. Probabilistic fracture mechanics calculations are presented to demonstrate how component failure probabilities can be managed through augmented inservice inspection programs.
    keyword(s): Design , Pipes , Surgery , Failure , Industrial plants , Nuclear power stations , Probability , Fatigue , Inspection , Leakage AND Corrosion ,
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      Life Prediction and Monitoring of Nuclear Power Plant Components for Service-Related Degradation

    URI
    https://yetl.yabesh.ir/yetl1/handle/yetl/125772
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    contributor authorFredric A. Simonen
    contributor authorStephen R. Gosselin
    date accessioned2017-05-09T00:05:50Z
    date available2017-05-09T00:05:50Z
    date copyrightFebruary, 2001
    date issued2001
    identifier issn0094-9930
    identifier otherJPVTAS-28407#58_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/125772
    description abstractThis paper describes industry programs to manage structural degradation and to justify continued operation of nuclear components when unexpected degradation has been encountered due to design materials and/or operational problems. Other issues have been related to operation of components beyond their original design life in cases where there is no evidence of fatigue crack initiation or other forms of structural degradation. Data from plant operating experience have been applied in combination with inservice inspections and degradation management programs to ensure that the degradation mechanisms do not adversely impact plant safety. Probabilistic fracture mechanics calculations are presented to demonstrate how component failure probabilities can be managed through augmented inservice inspection programs.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleLife Prediction and Monitoring of Nuclear Power Plant Components for Service-Related Degradation
    typeJournal Paper
    journal volume123
    journal issue1
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.1344237
    journal fristpage58
    journal lastpage64
    identifier eissn1528-8978
    keywordsDesign
    keywordsPipes
    keywordsSurgery
    keywordsFailure
    keywordsIndustrial plants
    keywordsNuclear power stations
    keywordsProbability
    keywordsFatigue
    keywordsInspection
    keywordsLeakage AND Corrosion
    treeJournal of Pressure Vessel Technology:;2001:;volume( 123 ):;issue: 001
    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
    yabeshDSpacePersian