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Formulation of the Stress Corrosion Crack Growth Rates for the Practical Use in the Integrity Assessment of Nuclear Reactor Components

[+] Author Affiliations
Masato Koshiishi, Satoru Aoike

Hitachi-GE Nuclear Energy Ltd., Hitachi-shi, Japan

Tsuneyuki Hashimoto

Hitachi Ltd., Hitachi-shi, Japan

Yuya Hideki

Chubu Electric Power Co., Inc., Omaezaki-shi, Japan

Paper No. PVP2018-84213, pp. V06BT06A010; 7 pages
doi:10.1115/PVP2018-84213
From:
  • ASME 2018 Pressure Vessels and Piping Conference
  • Volume 6B: Materials and Fabrication
  • Prague, Czech Republic, July 15–20, 2018
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 978-0-7918-5168-5
  • Copyright © 2018 by ASME

abstract

The Hashimoto-Koshiishi model was simplified from a mathematical viewpoint taking into consideration explicit crack growth rate (CGR) dependency on the stress intensity factor to enable practicable use of the model in the integrity assessment of boiling water reactor components. Then simplified equations were developed for different strain distribution cases in the model. The developed simplified equations were applied to analyze CGRs of cold worked stainless steels and the simulated weld heat affected zone of the primary loop recirculation piping and core shroud and these equations reproduced CGRs well.

Copyright © 2018 by ASME

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