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.

This content is only available via PDF.
You do not currently have access to this content.