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Flow Induced Vibration and Fretting Wear in PWR Fuel

[+] Author Affiliations
S. J. King, M. Y. Young, D. D. Seel, M. E. Conner, Roger Y. Lu

Westinghouse Nuclear Fuel, Columbia, SC

D. V. Paramonov

Westinghouse Science and Technology, Pittsburgh, PA

Paper No. ICONE10-22399, pp. 639-648; 10 pages
doi:10.1115/ICONE10-22399
From:
  • 10th International Conference on Nuclear Engineering
  • 10th International Conference on Nuclear Engineering, Volume 1
  • Arlington, Virginia, USA, April 14–18, 2002
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-3595-2 | eISBN: 0-7918-3589-8
  • Copyright © 2002 by ASME

abstract

Fuel rod fretting wear is due to complex combinations of factors. Excitation of the fuel rod and motion relative to its supports can be caused by coolant flow and mechanical forces. The amplitude of response for a given set of flow and mechanical forces is dependent on the fuel rod and its support system. The fuel rod mass and stiffness and location of supports along its length dictate the mode shapes and natural frequencies. The contact geometry between the support system and fuel rod is also an important factor. The two primary areas covered in this paper are 1) the types of flow conditions that may exist in a reactor core and how they would result in excitation of the fuel rod and 2) how the relative motion of the rod to its supports can result in fretting wear. Numerous testing techniques, ranging from microscopic, to single grid cell tests, to high temperature and flow full scale multiple fuel assembly tests, are discussed.

Copyright © 2002 by ASME

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