Evaluation of Fretting Damage of Zircaloy Cladding Tubes

[+] Author and Article Information
Olof Vingsbo

Uppsala University, Uppsala, Sweden; University of Houston, Texas

Ali R. Massih, Stig Nilsson

ABB Atom, S-721 63 Västerås, Sweden

J. Tribol 118(4), 705-710 (Oct 01, 1996) (6 pages) doi:10.1115/1.2831598 History: Received April 28, 1994; Revised January 05, 1995; Online January 24, 2008


The work is part of the search for a technique to study the fretting properties of the cladding of fuel rods in nuclear reactors. The strategy is to compare the fretting scars of specimens tested in a near-full-scale, nonradioactive simulator (so called fuel assembly endurance test) with scars on specimens tested under well controlled conditions in the laboratory. By systematic variations of the laboratory testing parameters it has proved possible to achieve scars with the same type of damage characteristics as those from the fuel assembly endurance test. This makes it possible to estimate, by deduction, the parameters that cause fretting damage under actual service conditions in a reactor.

Copyright © 1996 by The American Society of Mechanical Engineers
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