Paper Title:
Crack Initiation Factor by Impact Fretting Wear at INCONEL Alloy for Steam Generator Tube in Nuclear Power Plants
  Abstract

Inconel alloy such as alloy 600 and alloy 690 is widely used as the steam generator tube materials in the nuclear power plants. The impact fretting wear tests were performed to investigate wear mechanism between tube alloy and 409 stainless steel tube support plates in the simulated steam generator operating conditions, pressure of 15MPa, high temperature water of 290°C and low dissolved oxygen(<10 ppb). From investigation of wear test specimens by the SEM and EDS analysis, hammer imprint, which is known to be an actual damaged wear pattern, has been observed on the worn surface, and fretting wear mechanism was investigated. Wear progression of impact-fretting wear also has been examined. It was observed that titanium rich phase contributes to the formation of voids and cracks in sub-layer of fretting wear damage by impact fretting wear.

  Info
Periodical
Advanced Materials Research (Volumes 26-28)
Edited by
Young Won Chang, Nack J. Kim and Chong Soo Lee
Pages
1269-1272
DOI
10.4028/www.scientific.net/AMR.26-28.1269
Citation
C. Y. Park, J. K. Kim, T. R. Kim, S. Y. Cho, H. I. Jeon, "Crack Initiation Factor by Impact Fretting Wear at INCONEL Alloy for Steam Generator Tube in Nuclear Power Plants", Advanced Materials Research, Vols. 26-28, pp. 1269-1272, 2007
Online since
October 2007
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$32.00
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