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The Geometry of Steam Generator Tube and Its Relevance to the Occurrence of Stress Corrosion Cracking in Operating Nuclear Power Plants

[+] Author Affiliations
Deok Hyun Lee, Do Haeng Hur, Myung Sik Choi, Kyung Mo Kim, Jung Ho Han

Korea Atomic Energy Research Institute, Daejeon, Republic of Korea

Myung Ho Song

Korea Institute of Nuclear Safety, Daejeon, Republic of Korea

Paper No. PVP2010-25362, pp. 17-18; 2 pages
  • ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference
  • ASME 2010 Pressure Vessels and Piping Conference: Volume 7
  • Bellevue, Washington, USA, July 18–22, 2010
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 978-0-7918-4926-2 | eISBN: 978-0-7918-3878-5
  • Copyright © 2010 by ASME


Occurrences of a stress corrosion cracking in the steam generator tubes of operating nuclear power plants are closely related to the residual stress existing in the local region of a geometric change, that is, expansion transition, u-bend, ding, dent, bulge, etc. Therefore, information on the location, type and quantitative size of a geometric anomaly existing in a tube is a prerequisite to the activity of a non destructive inspection for an alert detection of an earlier crack and the prediction of a further crack evolution [1].

Copyright © 2010 by ASME



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