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

Author:

Ko P. L.1,Taponat M.-C.2,Zbinden M.3

Affiliation:

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

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

3. Electricite´ de France, DMTC, Les Renardie`res, 77250 Moret-sur-Loing, France

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.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

Reference21 articles.

1. Axisa, F., Paurobally, A., and Remond, A., 1989, “Predictive Analyses of Flow-Induced Vibration and Fretting Wear in Steam Generator Tubes,” Proceedings, International Symposium on Pressure Vessel Technology and Nuclear Codes & Standards, Seoul, Korea, pp. 57–75.

2. Blevins R. D. , 1983, “Vibration-Induced Wear of Heat Exchanger Tubes,” ASME Journal of Engineering Materials and Technology, Vol. 107, pp. 61–67.

3. Blevins, R. D., 1984, “A Rational Algorithm for Predicting Vibration-Induced Damage to Tube and Shell Heat Exchangers,” ASME Publ. No. G00269.

4. Connors H. J. , 1981, “Flow-Induced Vibration and Wear of Steam Generator Tubes,” Nuclear Technology, Vol. 55, pp. 311–331.

5. Crook, P., and Li, C. C., 1983, “The Elevated Temperature Metal-to-Metal Wear Behaviour of Selected Hardfacing Alloys,” Wear of Materials—1983, ASME Publ. No. H00254, pp. 272–279.

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