Article ID Journal Published Year Pages File Type
6759776 Nuclear Engineering and Design 2016 9 Pages PDF
Abstract
Results obtained from these tests have shown that alloy 316L is susceptible to SCC in supercritical water reactor conditions where the susceptibility of this alloy increases with temperature. Moreover, prior plastic deformation of 316L SS increased its susceptibility to environmental cracking in SCW.
Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
Preview
Stress corrosion cracking behavior of annealed and cold worked 316L stainless steel in supercritical water
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