“…In the same way, Chen et al [10] applied the FAVOR code to calculate the probabilities of conditional initiation/cleavage frequency of a RPV beltline region subjected to pressurized thermal shock events. Nagai et al [11] developed a probabilistic fracture mechanics (PFM) analysis code in order to rationally evaluate the failure probability of pipes, containing a circumferential crack on the inner surface, in the primary loop recirculation piping in Japanese boiling water reactor (BWR) plants. Hojo and co-workers [12] developed a PFM framework based on the Japan Society of Mechanical Engineers (JSME) rules so as to assess the leak probability time history and failure probability in 40 years operation of different components in Japanese pressurized water reactor (PWR) plants.…”