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

Journal Article · · JOM. Journal of the Minerals, Metals & Materials Society
 [1];  [2];  [3]
  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 Laboratory (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, Journal Name: JOM. Journal of the Minerals, Metals & Materials Society Journal Issue: 11 Vol. 68; ISSN 1047-4838
Publisher:
SpringerCopyright Statement
Country of Publication:
United States
Language:
English

References (10)

Overview no. 55 Wear-Mechanism maps journal January 1987
On fretting maps journal September 1988
Mixed fretting regime journal March 1995
Fretting-wear of zirconium alloys journal April 2002
Fretting wear of laterally supported tube journal October 2001
The study on grid-to-rod fretting wear models for PWR fuel journal December 2009
Comparative study on rod fretting behavior of different spacer spring geometries journal January 2009
Fretting wear behavior of a nuclear fuel rod under a simulated primary coolant condition journal April 2013
A multi-stage wear model for grid-to-rod fretting of nuclear fuel rods journal May 2014
Contact and Rubbing of Flat Surfaces journal August 1953

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