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 this data is reported and its application to the assessment of the project feature tests on large beam test pieces.
Use of Master Curve Technology for Assessing Shallow Flaws in a Reactor Pressure Vessel Material
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Taylor, N, Minnebo, P, Bass, RB, Siegele, D, Wallin, K, Kytka, M, Wintle, J, & Wintle, J. "Use of Master Curve Technology for Assessing Shallow Flaws in a Reactor Pressure Vessel Material." Proceedings of the ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference. Volume 6: Materials and Fabrication. Vancouver, BC, Canada. July 23–27, 2006. pp. 211-220. ASME. https://doi.org/10.1115/PVP2006-ICPVT-11-93640
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