Relationships between stress corrosion cracking tests and utility operating experience

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Description

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 ... continued below

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17 p.

Creation Information

Baum, Allen October 22, 1999.

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This article is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this article can be viewed below.

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  • Bettis Atomic Power Laboratory
    Publisher Info: Bettis Atomic Power Lab., West Mifflin, PA (United States)
    Place of Publication: West Mifflin, Pennsylvania

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Description

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.

Physical Description

17 p.

Notes

INIS; OSTI as DE00754893

Medium: P; Size: 17 pages

Source

  • 9th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors, Newport Beach, CA (US), 08/01/1999--08/05/1999

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  • Report No.: B-T-3274
  • Report No.: N00024-98-C-4064
  • Grant Number: AC11-98PN38206
  • Office of Scientific & Technical Information Report Number: 754893
  • Archival Resource Key: ark:/67531/metadc707469

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  • October 22, 1999

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  • Sept. 12, 2015, 6:31 a.m.

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  • April 7, 2017, 3:45 p.m.

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Baum, Allen. Relationships between stress corrosion cracking tests and utility operating experience, article, October 22, 1999; West Mifflin, Pennsylvania. (digital.library.unt.edu/ark:/67531/metadc707469/: accessed September 20, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.