Abstract:Dissimilar welds, used to join different sections in light water reactors, are potentially susceptible to stress corrosion cracking (SCC) in aqueous media, characteristic of nuclear plants. However, the study of these welds has been limited to evaluating weld material susceptibility in these media. Scarce data are available on crack growth rates due fundamentally to inadequate testing techniques. In order to address this lack of information, the crack growth rate at the interface of ferritic SA533B-1 alloy and… Show more
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