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Fatigue Crack Growth Curve for Austenitic Stainless Steels in PWR Environment

[+] Author Affiliations
Yuichiro Nomura, Hiroshi Kanasaki, Shigeki Suzuki

Mitsubishi Heavy Industries, Ltd.

Katsumi Sakaguchi

Japan Nuclear Energy Safety Organization

Paper No. PVP2006-ICPVT-11-93224, pp. 123-128; 6 pages
doi:10.1115/PVP2006-ICPVT-11-93224
From:
  • ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference
  • Volume 1: Codes and Standards
  • Vancouver, BC, Canada, July 23–27, 2006
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4752-7 | eISBN: 0-7918-3782-3
  • Copyright © 2006 by ASME

abstract

Reference fatigue crack growth rate curves for austenitic stainless steels in pressurized water reactors (PWR) environments were prescribed in JSME S NA1-2004(1) in Japan. The reference fatigue crack growth curve in PWR environment had been determined as a function of stress intensity factor range, temperature, load rising time and stress ratio. In order to confirm the applicability of the reference fatigue crack growth rate curve under high stress ratio, low rising time and low stress intensity range, fatigue crack propagation tests of austenitic stainless steels 316, 316 weld metal, 304 and 304 weld metal were carried out. It is concluded that the reference fatigue crack growth curve in PWR environment is applicable to predict fatigue crack growth rate of this study test conditions.

Copyright © 2006 by ASME

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