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.
1.
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,” Proceedings of the International Conference on Shallow Crack Fracture Mechanics
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, and Schwalbe
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, M.
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, E.
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,” J. Nucl. Mater.
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, pp. 1243
–1247
.Copyright © 2008
by American Society of Mechanical Engineers
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