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Evaluation of Fatigue Damage in LWR Water With and Without Threshold and Moderation Factor

[+] Author Affiliations
Makoto Higuchi

Ishikawajima-Harima Heavy Industries, Yokohama-shi, Japan

Kazuya Tsutsumi

Mitsubishi Heavy Industries, Takasago-shi, Japan

Katsumi Sakaguchi

Japan Power Engineering and Inspection Corporation, Hitachinaka-shi, Japan

Paper No. PVP2003-1774, pp. 97-111; 15 pages
doi:10.1115/PVP2003-1774
From:
  • ASME 2003 Pressure Vessels and Piping Conference
  • Pressure Vessel and Piping Codes and Standards
  • Cleveland, Ohio, USA, July 20–24, 2003
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-1694-X
  • Copyright © 2003 by ASME

abstract

During the past twenty years, the fatigue initiation life of LWR structural materials, carbon, low alloy and stainless steels has been shown to decrease remarkably in the simulated LWR (light water reactor) coolant environments. Several models for evaluating the effects of environment on fatigue life reduction have been developed based on published environmental fatigue data. Initially, based on Japanese fatigue data, Higuchi and Iida proposed a model for evaluating such effects quantitatively for carbon and low alloy steels in 1991. Thereafter, Chopra et al. proposed other models for carbon, low alloy and stainless steels by adding American fatigue data in 1993. Mehta developed a new model which features the threshold concept and moderation factor in Chopra’s model in 1995. All these models have undergone various revisions. In Japan, the MITI (Ministry of International Trade and Industry) guideline on environmental fatigue life reduction for carbon, low alloy and stainless steels was issued in September 2000, for evaluating of aged light water reactor power plants. The MITI guideline provide equations for calculations applicable only to stainless steel in PWR water and consequently Higuchi et al. proposed in 2002 a revised model for stainless steel which incorporates new equations for evaluation of environmental fatigue reduction in BWR water. The paper compares the latest versions of these models and discusses the conservativeness of the models by comparison of the models with available test data.

Copyright © 2003 by ASME

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