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Corrosion Fatigue Results for Alloy 690 Tubing in a PWR Secondary Environment

[+] Author Affiliations
Bruce A. Young

Babcock and Wilcox Company, Alliance, OH

Peter J. King

Babcock & Wilcox Canada, Cambridge, Ontario, Canada

Paper No. PVP2005-71044, pp. 67-72; 6 pages
  • ASME 2005 Pressure Vessels and Piping Conference
  • Volume 1: Codes and Standards
  • Denver, Colorado, USA, July 17–21, 2005
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4186-3 | eISBN: 0-7918-3763-7
  • Copyright © 2005 by ASME


Previous corrosion fatigue results [1,2,3] have shown no enhancement to the crack growth rate of Alloy 690 in a Pressurized Water Reactor (PWR) or a low dissolved oxygen (DO) concentration (less than 10 ppb) environment under open-circuit potential conditions. This research compared corrosion fatigue literature data for Alloy 690 plate, which used conventional compact tension, C(t), specimens; to Alloy 690 tests conducted using steam generator tubing (S-193). There was some concern that the results on plate material may not be representative of the behavior of steam generator tubing due to grain size, section thickness or other processing variables. The overall objective of this research was to determine if steam generator tubing response in a PWR secondary side environment could be modeled using the literature data from plate material. Fatigue crack growth rate data for Alloy 690, on an actual service heat of steam generator tubing in a low dissolved oxygen PWR secondary side environment, was generated using a circumferentially throughwall cracked tube specimen. The new data generated, along with the literature data, were compared to a modified corrosion fatigue model. The results showed the tube material behaved similarly to the plate material and thus standard specimen geometries, for example, compact tension specimens, tested on thick section materials could be used to characterize tube material response under these environmental conditions.

Copyright © 2005 by ASME



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