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- W2424103675 abstract "A number of experimental studies have been performed since the examination of tubes pulled from nuclear power plants revealed the presence of lead associated with secondary side mixed Inter/Trans-Granular Stress Corrosion Cracking (IG/TG SCC). Various testing methods were employed on Alloys 600, 690, and 800, and the available studies involve Constant Elongation Rate Tests (CERTs), constant deformation tests in caustic, neutral, or acidic solutions, as well as electrochemical tests and surface layer analyses. Complementary tests are presented on the influence of the solution temperature, and of the elongation rate in CERTS. An analysis of the various results obtained is interpreted in the framework of a mechanism involving both anodic dissolution and fracture events. This analysis indicates that such a mechanism can account for the influence of lead by considering a lowering of the global activation energy of the repassivation processes without changes in the apparent activation energy of the crack growth rate. Comparison to in-service cracking also indicates that the influence of lead seems more predominant in neutral pH solutions than in caustic or acidic ones." @default.
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- W2424103675 date "1995-12-31" @default.
- W2424103675 modified "2023-09-23" @default.
- W2424103675 title "Some considerations about the possible mechanisms of lead assisted stress corrosion cracking of steam generator tubing" @default.
- W2424103675 hasPublicationYear "1995" @default.
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