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Fretting Wear Between Supporting Grids and Cladding Tubes of Nuclear Fuel Rod

[+] Author Affiliations
Young-Chang Park, Young-Ze Lee

Sungkyunkwan University

Yong-Hwan Kim, Seung-Jae Lee

Korea Nuclear Fuel Company

Paper No. IMECE2006-13625, pp. 97-99; 3 pages
  • ASME 2006 International Mechanical Engineering Congress and Exposition
  • Energy Conversion and Resources
  • Chicago, Illinois, USA, November 5 – 10, 2006
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-4783-7 | eISBN: 0-7918-3790-4
  • Copyright © 2006 by ASME


The experimental investigation was performed to find the associated changes in characteristics of fretting wear with various water temperatures. Fretting can be defined as the oscillatory motion with very small amplitudes, which usually occur between two contacting surfaces. The fretting wear, which occurs between cladding tubes of nuclear fuel rod and grids, causes in damages the cladding tubes by flow induced vibration in a nuclear reactor. In this paper, the fretting wear tests were carried out using the zirconium alloy tubes and the grids with increasing the water temperature. The tube materials in water of 20°C, 50°C and 80°C were tested with the applied loads from 5N up to 25N and the relative amplitude of 200μm. The worn surfaces were observed by SEM, EDX analysis and 2D surface profiler. As the water temperature increased, the wear volume was decreased, but oxide layer was increased on the worn surface. The abrasive wear mechanism was observed at water temperature of 20°C and adhesive wear mechanism occurred at water temperature of 50°C, 80°C. As the water temperature increased, surface micro-hardness was decreased, but wear depth and wear width were decreased due to increasing stick phenomenon. Stick regime occurred due to the formation of oxide layer on the worn surface with increasing water temperatures.

Copyright © 2006 by ASME



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