Corrosion fatigue initiation and short crack growth behaviour of austenitic stainless steels under light water reactor conditions

Author:

Seifert H.P.,Ritter S.,Leber H.J.

Funder

Eidgenössisches Nuklearsicherheitsinspektorat

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference30 articles.

1. Environmentally-Assisted Cracking in Austenitic Light Water Reactor Structural Materials – Final Report of the KORA-I Project, PSI Report No. 09–03;Seifert,2009

2. O.K. Chopra, W.J. Shack, Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials, NUREG/CR-6909, US NRC, Washington DC, USA, February 2007. Available on: (accessed on September 2011).

3. A review of the effects of coolant environments on the fatigue life of LWR structural materials;Chopra;Journal of Pressure Vessel Technology,2009

4. D.R. Tice, D. Green, A. Toft, Environmentally Assisted Fatigue Gap Analysis and Roadmap for Future Research: Gap Analysis Report, 1023012, EPRI, Palo Alto, CA, USA, December 2011. Available on: (accessed on January 2012).

5. Fatigue crack growth curve for austenitic stainless steels in BWR environment;Itatani;Journal of Pressure Vessel Technology,2001

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