Effects of pH on lead-induced passivity degradation of nuclear steam generator tubing alloy in high temperature crevice chemistries
Author:
Funder
Natural Sciences and Engineering Research Council of Canada
Atomic Energy of Canada Limited
Publisher
Elsevier BV
Subject
Electrochemistry,General Chemical Engineering
Reference65 articles.
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2. Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors: part 1;Staehle;Corrosion,2003
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4. Assessment of and proposal for a mechanistic interpretation of the SCC of high nickel alloys;Staehle,2003
5. The mode of stress corrosion cracking in Ni-based alloys in high temperature water containing lead;Hwang;Journal of Nuclear Materials,1999
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