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    Use of Fracture Mechanics in Reactor Vessel Surveillance

    Source: Journal of Fluids Engineering:;1971:;volume( 093 ):;issue: 002::page 259
    Author:
    T. R. Mager
    ,
    S. E. Yanichko
    DOI: 10.1115/1.3425222
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper presents the basis for utilizing fracture mechanics technology based upon data obtained from small Charpy V-notch specimens incorporated in reactor vessel surveillance programs. Included is a brief background on linear elastic fracture mechanics and a discussion of reactor surveillance programs in general. Data obtained from published literature are organized and an empirical approach is proposed to utilize the fracture mechanics technique in surveillance programs. A typical problem is included to demonstrate that the approach discussed can be successfully applied to nuclear pressure vessel safety analysis.
    keyword(s): Fracture mechanics , Surveillance , Reactor vessels AND Safety ,
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      Use of Fracture Mechanics in Reactor Vessel Surveillance

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    http://yetl.yabesh.ir/yetl1/handle/yetl/152578
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    contributor authorT. R. Mager
    contributor authorS. E. Yanichko
    date accessioned2017-05-09T01:01:06Z
    date available2017-05-09T01:01:06Z
    date copyrightJune, 1971
    date issued1971
    identifier issn0098-2202
    identifier otherJFEGA4-27379#259_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/152578
    description abstractThis paper presents the basis for utilizing fracture mechanics technology based upon data obtained from small Charpy V-notch specimens incorporated in reactor vessel surveillance programs. Included is a brief background on linear elastic fracture mechanics and a discussion of reactor surveillance programs in general. Data obtained from published literature are organized and an empirical approach is proposed to utilize the fracture mechanics technique in surveillance programs. A typical problem is included to demonstrate that the approach discussed can be successfully applied to nuclear pressure vessel safety analysis.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleUse of Fracture Mechanics in Reactor Vessel Surveillance
    typeJournal Paper
    journal volume93
    journal issue2
    journal titleJournal of Fluids Engineering
    identifier doi10.1115/1.3425222
    journal fristpage259
    journal lastpage264
    identifier eissn1528-901X
    keywordsFracture mechanics
    keywordsSurveillance
    keywordsReactor vessels AND Safety
    treeJournal of Fluids Engineering:;1971:;volume( 093 ):;issue: 002
    contenttypeFulltext
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