4.7 Article

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

Journal

CORROSION SCIENCE
Volume 55, Issue -, Pages 61-75

Publisher

PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.corsci.2011.10.005

Keywords

Stainless steel; Corrosion fatigue; Reactor conditions

Funding

  1. Swiss Federal Nuclear Safety Inspectorate (ENSI)

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The corrosion fatigue crack growth behaviour of different wrought low-carbon and stabilised austenitic stainless steels was characterised under simulated boiling water and primary pressurised water reactor conditions by cyclic fatigue tests with pre-cracked fracture mechanics specimens in the temperature range from 70 to 320 degrees C. The major parameter effects and critical conjoint threshold conditions, which result in relevant environmental acceleration of fatigue crack growth are discussed and summarised. Furthermore, the observed corrosion fatigue behaviour is compared with the corresponding (corrosion) fatigue curves in the ASME and JSME boiler and pressure vessel code or open literature and conclusions with regard to their adequacy and conservatism are given. (C) 2011 Elsevier Ltd. All rights reserved.

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