Modeling of complex wear behavior associated with grid-to-rod fretting in light water nuclear reactors

Journal Article · Wed Sep 21 00:00:00 EDT 2016 · JOM. Journal of the Minerals, Metals & Materials Society

DOI:https://doi.org/10.1007/s11837-016-2113-9· OSTI ID:1327602

Blau, P. J. ^[1]; Qu, J. ^[2]; Lu, R. ^[3]

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1. Bluau Tribology Consulting, Enka, NC (United States)
2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
3. Westinghouse Electric Company, LLC, Columbia, SC (United States)

One significant concern in the operation of light water nuclear reactors is the fretting wear damage to fuel cladding from flow-induced vibrations. For years, research on the grid-to-rod fretting (GTRF) phenomena has been underway in countries where nuclear power production is a significant industry. Under the auspices of the U.S. Department of Energy Consortium for Advanced Simulation of Light Water Reactors, an effort has been underway to develop and test an engineering wear model for zirconium alloy fuel rod cladding against a supporting grid. Furthermore, the multi-stage model accounts for oxide layers and wear rate transitions. Our paper describes the basis for a GTRF engineering wear model, the physical significance of the wear factor it contains, and recent progress toward model validation based on a fretting wear testing apparatus that accounts for coolant temperature, pressure, and the presence of periodic impacts (gaps) in grid/rod contact.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• Grant/Contract Number: AC05-00OR22725
• OSTI ID: 1327602
• Journal Information: JOM. Journal of the Minerals, Metals & Materials Society, Vol. 68, Issue 11; ISSN 1047-4838
• Publisher: Springer
• Country of Publication: United States
• Language: English

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