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Verification of Probabilistic Fracture Mechanics Analysis Code PASCAL Through Benchmark Analyses With FAVOR

[+] Author Affiliations
Yinsheng Li, Shumpei Uno, Jinya Katsuyama

Japan Atomic Energy Agency, Tokai-mura, Japan

Terry Dickson

Oak Ridge National Laboratory, Oak Ridge, TN

Mark Kirk

US Nuclear Regulatory Commission, Washington, DC

Paper No. PVP2017-66004, pp. V01BT01A007; 8 pages
doi:10.1115/PVP2017-66004
From:
  • ASME 2017 Pressure Vessels and Piping Conference
  • Volume 1B: Codes and Standards
  • Waikoloa, Hawaii, USA, July 16–20, 2017
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 978-0-7918-5791-5
  • Copyright © 2017 by ASME

abstract

A probabilistic fracture mechanics (PFM) analysis code called 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 based on Japanese data and Japanese methods published for or provided in Japanese codes and standards. To verify this code, benchmark analyses were carried out using the FAVOR code, which was developed in the United States and has been utilized in nuclear regulation. The results of these analyses confirmed with great confidence the applicability of PASCAL to failure probability and frequency evaluation of Japanese RPVs. An outline of PASCAL, the benchmark analysis conditions and analysis results are reported in this paper.

Copyright © 2017 by ASME

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