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RESEARCH PAPERS

Wear Studies of Materials for Tubes and Antivibration Bars in Nuclear Steam Generators

[+] Author and Article Information
P. L. Ko

National Research Council of Canada, Institute for Sensor and Control Technology, 3250 East Mall, Vancouver, British Columbia, V6T 1W5 Canada

M.-C. Taponat

Department of Mechanical Engineering, University of British Columbia, Vancouver, British Columbia, V6T 1Z4 Canada

M. Zbinden

Electricité de France, DMTC, Les Renardières, 77250 Moret-sur-Loing, France

J. Pressure Vessel Technol 118(3), 287-300 (Aug 01, 1996) (14 pages) doi:10.1115/1.2842191 History: Received March 27, 1995; Revised November 29, 1995; Online February 11, 2008

Abstract

Wear occurs as a result of relative motion at the interface of two contacting bodies. In nuclear power steam generators, high flow rates can induce vibration of the tubes resulting in wear damage due to impact and sliding contacts between the tubes and their supports. A research project aiming to gain better understanding of the mechanisms and mechanics involved in vibratory wear and to develop a more versatile predictive wear model was carried out. Combinations of Inconel tubes against flat antivibration bars of 403 SS and electrolytic-chrome plated Inconel 600 were tested under conditions of reciprocating sliding and impacting in water at room temperature and at 250°C. The results show that, depending on the material combinations and he loading conditions, distinctively different wear mechanisms and often drastically different wear rates can occur.

Copyright © 1996 by The American Society of Mechanical Engineers
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