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AbstractAbstract
[en] Several utility steam generator and stress corrosion cracking databases are synthesized with the view of identifying the crevice chemistry that is most consistent with the plant cracking data. Superheated steam and neutral solution environments are found to be inconsistent with the large variations in the observed SCC between different plants, different support plates within a plant, and different crevice locations. While the eddy current response of laboratory tests performed with caustic chemistries approximates the response of the most extensively affected steam generator tubes, the crack propagation kinetics in these tests differ horn plant experience. The observations suggest that there is a gradual conversion of the environment responsible for most steam generator ODSCC from a concentrated, alkaline-forming solution to a progressively more steam-enriched environment
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22 Oct 1999; 18 p; 9. International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors; Newport Beach, CA (United States); 1-5 Aug 1999; N00024--98-C-4064; AC11-98PN38206; Also available from OSTI as DE00754893; PURL: https://www.osti.gov/servlets/purl/754893-4ACuFQ/webviewable/
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