NDLI: Verification of Probabilistic Fracture Mechanics Analysis Code Through Benchmark Analyses

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Li, Yinsheng Uno, Shumpei Masaki, Koichi Katsuyama, Jinya Dickson, Terry Kirk, Mark
Copyright Year	2018
Abstract	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.
Sponsorship	Pressure Vessels and Piping Division
File Format	PDF
ISBN	9780791851593
DOI	10.1115/PVP2018-84963
Volume Number	Volume 1B: Codes and Standards
Conference Proceedings	ASME 2018 Pressure Vessels and Piping Conference
Language	English
Publisher Date	2018-07-15
Publisher Place	Prague, Czech Republic
Access Restriction	Subscribed
Subject Keyword	Nuclear power Fracture mechanics Reactor vessels Irradiation (radiation exposure) Thermal shock Embrittlement Probability Neutrons Failure
Content Type	Text
Resource Type	Article

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Verification of Probabilistic Fracture Mechanics Analysis Code Through Benchmark Analyses