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

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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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VL - 130

JO - Journal of Pressure Vessel Technology

JF - Journal of Pressure Vessel Technology

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