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    Use of Master Curve Technology for Assessing Shallow Flaws in a Reactor Pressure Vessel Material

    Source: Journal of Pressure Vessel Technology:;2008:;volume( 130 ):;issue: 003::page 31407
    Author:
    B. R. Bass
    ,
    D. Siegele
    ,
    K. Wallin
    ,
    M. Kytka
    ,
    J. Wintle
    ,
    N. Taylor
    ,
    P. Minnebo
    DOI: 10.1115/1.2937742
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In the NESC-IV project, an experimental/analytical program was performed to develop validated analysis methods for transferring fracture toughness data to shallow flaws in reactor pressure vessels subject to biaxial loading in the lower-transition temperature region. Within this scope, an extensive range of fracture tests was performed on material removed from a production-quality reactor pressure vessel. The master curve analysis of these data is reported and its application to the assessment of the project feature tests on large beam test pieces is discussed.
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      Use of Master Curve Technology for Assessing Shallow Flaws in a Reactor Pressure Vessel Material

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    http://yetl.yabesh.ir/yetl1/handle/yetl/139198
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    contributor authorB. R. Bass
    contributor authorD. Siegele
    contributor authorK. Wallin
    contributor authorM. Kytka
    contributor authorJ. Wintle
    contributor authorN. Taylor
    contributor authorP. Minnebo
    date accessioned2017-05-09T00:30:16Z
    date available2017-05-09T00:30:16Z
    date copyrightAugust, 2008
    date issued2008
    identifier issn0094-9930
    identifier otherJPVTAS-28496#031407_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/139198
    description abstractIn the NESC-IV project, an experimental/analytical program was performed to develop validated analysis methods for transferring fracture toughness data to shallow flaws in reactor pressure vessels subject to biaxial loading in the lower-transition temperature region. Within this scope, an extensive range of fracture tests was performed on material removed from a production-quality reactor pressure vessel. The master curve analysis of these data is reported and its application to the assessment of the project feature tests on large beam test pieces is discussed.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleUse of Master Curve Technology for Assessing Shallow Flaws in a Reactor Pressure Vessel Material
    typeJournal Paper
    journal volume130
    journal issue3
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.2937742
    journal fristpage31407
    identifier eissn1528-8978
    treeJournal of Pressure Vessel Technology:;2008:;volume( 130 ):;issue: 003
    contenttypeFulltext
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