Abstract
Abstract The implementation of probabilistic fracture mechanics (PFM) on integrity assessment standards of reactor pressure vessels (RPVs) is not yet actualized in Japan. The most recent information on how PFM will be used in the near future is provided by the guideline JEAG 4640-2018, which describes a standard approach for evaluating the failure frequency of RPVs based on PFM. Central Research Institute of Electric Power Industry is creating a new PFM analysis code FERMAT (Fracture mechanics Evaluation of RPV MATerials) for future application of PFM in Japan. Our code is based on JEAG 4640-2018 and has a minimum design for practical usage in RPV structural integrity assessments. With a graphical user interface, all processes can be handled in a single piece of code. In the present study, calculation results by FERMAT were compared with another Japanese PFM code PASCAL4 with a model case targeting Japanese RPV. The distribution of temperature and stress evaluated by FERMAT and PASCAL4 were very similar. The stress intensity factor calculated by FERMAT and PASCAL4 was well corresponding with each other. Additionally, sampled values for reference temperature for nil-ductile transition were confirmed. The probability and the frequency of crack initiation were compared between FERMAT and PASCAL4. The outcomes assessed using those codes were closely related to one another.
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