SCC crack growth rate of cold worked 316L stainless steel in PWR environment
Abstract
Many component failures in nuclear power plants were found to be caused by stress corrosion cracking (SCC) of cold worked austenitic steels. Some of the pressure boundary component materials are even cold worked up to 35% plastic deformation, leaving high residual stress and inducing high growth rate of corrosion crack. Controlling water chemistry is one of the best counter measure to mitigate this problem. In this work, the effects of...
Paper Details
Title
SCC crack growth rate of cold worked 316L stainless steel in PWR environment
Published Date
Jan 1, 2015
Journal
Volume
456
Pages
228 - 234
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