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Comparison of Predicted and Observed Fretting-Wear Damage in Nuclear Steam Generators

[+] Author Affiliations
N. J. Fisher, Y. Han, F. M. Guérout, V. P. Janzen

Atomic Energy of Canada, Ltd., Chalk River, Ontario, Canada

Paper No. PVP2005-71390, pp. 535-545; 11 pages
doi:10.1115/PVP2005-71390
From:
  • ASME 2005 Pressure Vessels and Piping Conference
  • Volume 4: Fluid Structure Interaction
  • Denver, Colorado, USA, July 17–21, 2005
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4189-8 | eISBN: 0-7918-3763-7
  • Copyright © 2005 by ASME

abstract

Fretting-wear of nuclear heat exchange equipment is addressed at the design stage to demonstrate that components will meet their design life. Atomic Energy of Canada Limited (AECL) has developed a methodology to predict the progression of fretting-wear damage using the combination of predicted work-rates from a finite element model and experimentally-derived wear coefficients. The predicted progression of fretting-wear damage in a recent steam generator design is compared to inspection results from steam generators in a mid-life plant. The predicted wear is similar to the maximum observed wear. Therefore, AECL’s methodology is shown to provide reasonable quantitative predictions of the progression of fretting-wear.

Copyright © 2005 by ASME

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