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Improvement of Probabilistic Fracture Mechanics Analysis Code for Reactor Piping Considering Large Earthquakes

[+] Author Affiliations
Yoshihito Yamaguchi, Jinya Katsuyama, Makoto Udagawa, Kunio Onizawa, Yutaka Nishiyama, Yinsheng Li

Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan

Paper No. ICONE22-30643, pp. V001T03A022; 8 pages
doi:10.1115/ICONE22-30643
From:
  • 2014 22nd International Conference on Nuclear Engineering
  • Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues
  • Prague, Czech Republic, July 7–11, 2014
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-4589-9
  • Copyright © 2014 by ASME

abstract

The probabilistic fracture mechanics analysis code PASCAL-SP is improved by introducing crack-growth evaluation methods based on J-integrals, including calculation functions of J-integral values for semi-elliptical surfaces and through-wall cracks in pipes. Using the improved PASCAL-SP, sensitivity analyses that varied parameters such as earthquake magnitude were carried out on the basis of probabilistic evaluation. Results obtained from sensitivity analyses are also presented, e.g., the effect of earthquake magnitude on failure probability. The improved PASCAL-SP makes evaluation of the failure probability of piping under large seismic loading possible.

Copyright © 2014 by ASME

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