Growth Model of Circumferential Outer Diameter Stress Corrosion Crack in Retired Steam Generator Tube of Kori 1 Nuclear Power Plant

Abstract:

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Growth model of a circumferential outer diameter stress corrosion crack (ODSCC) in a retired steam generator tube of the Kori 1 nuclear power plant was proposed based on extensive destructive examinations of the pulled tubes of Alloy 600 from the Kori 1 plant. A small ODSCC grows in a lateral direction as well as a forward direction until it meets a neighboring ODSCC which also grows in a lateral direction as well as a forward direction. And then, the two ODSCCs which meet on the same circumferential plane are consolidated into a single ODSCC. By repeating such a consolidation process with time, it seems that the apparent growth rate of an ODSCC in the lateral direction is much faster than that in the forward direction. Growth model of a circumferential ODSCC from a retired steam generator tube of the Kori 1 plant reveals that many ODSCCs are initiated and grow in both directions independently until they meet and finally they are consolidated.

Info:

Periodical:

Solid State Phenomena (Volumes 124-126)

Edited by:

Byung Tae Ahn, Hyeongtag Jeon, Bo Young Hur, Kibae Kim and Jong Wan Park

Pages:

1529-1532

DOI:

10.4028/www.scientific.net/SSP.124-126.1529

Citation:

D. J. Kim et al., "Growth Model of Circumferential Outer Diameter Stress Corrosion Crack in Retired Steam Generator Tube of Kori 1 Nuclear Power Plant", Solid State Phenomena, Vols. 124-126, pp. 1529-1532, 2007

Online since:

June 2007

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$35.00

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