Paper Title:
Wear Scar Progression of Impact-Fretting at Elevated Temperature for Steam Generator Tubes in Nuclear Power Plants
  Abstract

Fretting wear generated by flow induced vibration is one of the important degradation mechanisms of steam generator tubes in the nuclear power plants. Understanding of tube wear characteristics is very important to keep the integrity of the steam generator tubes to secure the safety of the nuclear power plants. Experimental examination has been performed for the purpose of investigating the impact fretting. Test material is alloy 690 tube and 409 stainless steel tube supports. From the results of experiments, wear scar progression is investigated in the case of impact-fretting wear test of steam generator tubes under plant operating conditions such as pressure of 15MPa, high temperature of 290C and low dissolved oxygen. Hammer imprint that is actual damaged wear pattern, has been observed on the worn surface. From investigation of wear scar pattern, wear mechanism was initially the delamination wear due to cracking the hard oxide film and finally transferred to the stable impact-fretting pattern.

  Info
Periodical
Key Engineering Materials (Volumes 326-328)
Edited by
Soon-Bok Lee and Yun-Jae Kim
Pages
1251-1254
DOI
10.4028/www.scientific.net/KEM.326-328.1251
Citation
C. Y. Park, J. K. Lee, "Wear Scar Progression of Impact-Fretting at Elevated Temperature for Steam Generator Tubes in Nuclear Power Plants", Key Engineering Materials, Vols. 326-328, pp. 1251-1254, 2006
Online since
December 2006
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Price
$32.00
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