STRESS CORROSION CRACKING OF SCWR CANDIDATE ALLOYS: A REVIEW OF PUBLISHED RESULTS
The 5th International Symposium on SuperCritical Water-cooled Reactors - 2011 March 13-16


Presented at:
The 5th International Symposium on SuperCritical Water-cooled Reactors
2011 March 13-16
Location:
Vancouver,Canada
Session Title:
Materials VI (SCC)

Authors:
Wenyue Zheng (Natural Resources Canada)
Jingli Luo (University of Alberta)
Ming Li (University of Alberta)
David Guzonas (Atomic Energy of Canada Limited)
William Cook (University of New Brunswick)
  

Abstract

Research on the development of supercritical water-cooled reactors (SCWRs) has generated a large pool of corrosion and stress-corrosion data in the open literature [1]. These data complement other aspects of reported materials properties such as creep and irradiation damage as well as microstructural degradation under various exposure/testing conditions. Unlike mechanical performance, the stress corrosion cracking (SCC) susceptibility of an alloy in a given environment can be affected by many factors including alloy composition and microstructure (including the degree of cold-working), chemistry of the environment, and the mechanical loading condition including the rate of loading (the so-called strain-rate). For in-core materials, the amount of neutron damage to which the alloy is subject also plays a key role in its SCC susceptibility. A summary is provided in this paper of the key findings from a survey of SCC test results published since the 1950s.

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