Use of master curve technology for assessing shallow flaws in a reactor pressure vessel material

N. Taylor, P. Minnebo, B. R. Bass, D. Siegele, Kim Wallin, M. Kytka, J. Wintle

    Research output: Contribution to journalArticleScientificpeer-review

    2 Citations (Scopus)

    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.
    Original languageEnglish
    Number of pages11
    JournalJournal of Pressure Vessel Technology
    Volume130
    Issue number3
    DOIs
    Publication statusPublished - 2008
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Pressure vessels
    Defects
    Superconducting transition temperature
    Fracture toughness

    Cite this

    Taylor, N. ; Minnebo, P. ; Bass, B. R. ; Siegele, D. ; Wallin, Kim ; Kytka, M. ; Wintle, J. / Use of master curve technology for assessing shallow flaws in a reactor pressure vessel material. In: Journal of Pressure Vessel Technology. 2008 ; Vol. 130, No. 3.
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    Use of master curve technology for assessing shallow flaws in a reactor pressure vessel material. / Taylor, N.; Minnebo, P.; Bass, B. R.; Siegele, D.; Wallin, Kim; Kytka, M.; Wintle, J.

    In: Journal of Pressure Vessel Technology, Vol. 130, No. 3, 2008.

    Research output: Contribution to journalArticleScientificpeer-review

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    AU - Taylor, N.

    AU - Minnebo, P.

    AU - Bass, B. R.

    AU - Siegele, D.

    AU - Wallin, Kim

    AU - Kytka, M.

    AU - Wintle, J.

    PY - 2008

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    AB - 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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    M3 - Article

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    JO - Journal of Pressure Vessel Technology

    JF - Journal of Pressure Vessel Technology

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