Use of Master Curve Technology for Assessing Shallow Flaws in a Reactor Pressure Vessel Material
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 lowertransition 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.
TAYLOR Nigel;
MINNEBO Philip;
SIEGELE Dieter;
WALLIN Kim;
WINTLE J.;
KYTKA Milos;
BASS Richard;
2006-09-28
American Society Of Mechanical Engineers (ASME)
JRC33641
https://publications.jrc.ec.europa.eu/repository/handle/JRC33641,
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