Paper Title:
Wear Characteristics of Tube-Support Components for a Nuclear Steam Generator under Fretting Conditions
  Abstract

Tubes in nuclear steam generators are held up by supports because the tubes are long and slender. Fluid flows of high-pressure and high-temperature flows in the tubes cause oscillating motions between tubes and supports. This is called as FIV (flow induced vibration) which cause fretting wear in contact part of tube-support. The reduction of tube thickness due to fretting wear of tube-support can threaten the safety of nuclear power plant. Therefore, a research on the fretting wear characteristics of tube-support is required. This work is focused on investigations of fretting wear characteristics and wear mechanisms of tube-support. Results show that the wear rate of tube is proportional to that of support and that with increasing the water temperature the wear volume of tube-support decreases because the oxidation rate decreases due to reduction of the oxygen concentration in contact surfaces. Also, the wear mechanisms of tube-support are abrasive and oxidational wear.

  Info
Periodical
Solid State Phenomena (Volume 120)
Edited by
Young-Jin Kim
Pages
181-186
DOI
10.4028/www.scientific.net/SSP.120.181
Citation
S. H. Jeong, Y. Z. Lee, "Wear Characteristics of Tube-Support Components for a Nuclear Steam Generator under Fretting Conditions", Solid State Phenomena, Vol. 120, pp. 181-186, 2007
Online since
February 2007
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Price
$32.00
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