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Li, Y.; 宇野 隼平*; 眞崎 浩一; 勝山 仁哉; Dickson, T.*; Kirk, M.*
Proceedings of 2018 ASME Pressure Vessels and Piping Conference (PVP 2018), 11 Pages, 2018/07
A probabilistic fracture mechanics (PFM) analysis code PASCAL has been developed in Japan Atomic Energy Agency to evaluate failure probabilities and failure frequencies of Japanese reactor pressure vessels (RPVs) considering pressurized thermal shock (PTS) events and neutron irradiation embrittlement, based on Japanese methods and data. To verify PASCAL, we have been carrying out benchmark analyses with a PFM code FAVOR which has been developed in the United States and utilized in nuclear regulation. Through two year activities, the applicability of PASCAL in failure probability and failure frequency evaluation of Japanese RPVs was confirmed with great confidence. The analysis conditions and results are provided in this paper.
Li, Y.; 宇野 隼平*; 勝山 仁哉; Dickson, T.*; Kirk, M.*
Proceedings of 2017 ASME Pressure Vessels and Piping Conference (PVP 2017) (CD-ROM), 8 Pages, 2017/07
Probabilistic fracture mechanics (PFM) analysis code PASCAL has been developed by the Japan Atomic Energy Agency to evaluate failure frequencies of Japanese reactor pressure vessels (RPVs) during pressurized thermal shock (PTS) events base on Japanese data and Japanese methods published for or prescribed in the Japanese regulations and standards. To verify this code, benchmark analyses were carried out with FAVOR code which was developed in United States and has been utilized in nuclear regulation. Through the benchmark analyses, the applicability of PASCAL in failure frequency evaluation of Japanese RPVs was confirmed with great confidence. The outline of PASCAL, the benchmark analysis conditions and results are provided in this paper.