Paper Title:
Development of Wear Test System for Steam Generator Tubes in Nuclear Power Plants
  Abstract

In steam generators of nuclear power plants, flow-induced vibration (FIV) can lead to tube damage by fretting-wear occurred due to impact and sliding movement between the tubes and their supports. There have been many studies and test results on wear damage of steam generator tubes but they were not reflected the mechanical and chemical conditions accurately. KEPRI nuclear power laboratory developed a wear test system, which is able to control the motion of impact and sliding simultaneously in the pressurized high temperature water-chemistry conditions. Some wear tests were performed to verify the stable operation for the wear test. This wear test system with new concepts was described briefly, and some data for verifying its performance have been shown in the cases of the selected some test results. In the test, Alloy 690 was used for tube materials and 409 stainless steel for support plates. A little data deviation was obtained and stability of system operation was investigated.

  Info
Periodical
Key Engineering Materials (Volumes 297-300)
Edited by
Young-Jin Kim, Dong-Ho Bae and Yun-Jae Kim
Pages
1418-1423
DOI
10.4028/www.scientific.net/KEM.297-300.1418
Citation
C. Y. Park, Y. S. Lee, M. H. Boo, "Development of Wear Test System for Steam Generator Tubes in Nuclear Power Plants ", Key Engineering Materials, Vols. 297-300, pp. 1418-1423, 2005
Online since
November 2005
Export
Price
$32.00
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