A probabilistic fracture mechanics (PFM) analysis code PASCAL has been developed by Japan Atomic Energy Agency based on Japanese methods and data to evaluate failure probabilities and failure frequencies of Japanese reactor pressure vessels (RPVs) considering pressurized thermal shock (PTS) events and neutron irradiation embrittlement. To verify PASCAL, we have been performing benchmark analyses by using a PFM code FAVOR which has been developed in the United States and utilized in nuclear regulation. Based on 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, approaches and results are given in this paper.
Verification of Probabilistic Fracture Mechanics Analysis Code Through Benchmark Analyses
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Li, Y, Uno, S, Masaki, K, Katsuyama, J, Dickson, T, & Kirk, M. "Verification of Probabilistic Fracture Mechanics Analysis Code Through Benchmark Analyses." Proceedings of the ASME 2018 Pressure Vessels and Piping Conference. Volume 1B: Codes and Standards. Prague, Czech Republic. July 15–20, 2018. V01BT01A075. ASME. https://doi.org/10.1115/PVP2018-84963
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