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.
Issue Section:
Research Papers
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.
6.
Fisher, N. J., Tayloy, C. E., and Pettigrew, M. J., 1990, “Fuel Element Vibration and Bearing Pad to Pressure Tube Fretting,” Atomic Energy of Canada Report, AECL-10164.
7.
Frick, T. M., Sobek, T. E., and Reavis, J. R., 1984, “Overview on the Development and Implementation of Methodologies to Compute Vibration and Wear of Steam Generator Tubes,” ASME Publ. No. G00269, Symposium on Flow-Induced Vibrations, Vol. 3, pp. 149–161.
8.
Fricker, H. W., 1972, “Fretting in Tube Supports of Heat Exchangers,” I. Mech. E. London, Proceedings, Conference on Component Design in High-Temperature Reactorsusing Helium as a Coolant, Paper No. 5.
9.
Gawne, D. T., and Ma, U., 1987, “Wear Mechanisms in Electroless Nickel Coatings,” Wear of Materials—1987, ASME Publ. No. H0376, pp. 515–533.
10.
Ko
P. L.
1985
, “The Significance of Shear and Normal Force Components on Tube Wear due to Fretting and Periodic Impacting
,” Wear
, Vol. 106
(1–3
), pp. 261
–281
.11.
Ko
P. L.
1987
, “Metallic Wear—A Review, with Special Reference to Vibration-Induced Wear in Power Plant Components
,” Tribology International
, Vol. 20
(2
), pp. 66
–78
.12.
Ko
P. L.
Basista
H.
1984
, “Correlation of Support Impact Force and Fretting-Wear for a Heat Exchanger Tube
,” ASME JOURNAL OF PRESSURE VESSEL TECHNOLOGY
, Vol. 106
, pp. 69
–77
.13.
Ko
P. L.
Magel
E. E.
1989
, “Impact and Sliding Wear in Steam Generators and Heat Exchangers: New Experimental Test Rig and Wear Model
,” ASME PVP
-Vol. 154
, Flow-Induced Vibration—1989, pp. 63
–69
.14.
Ko, P. L., Robertson, M. F., and Magel, E. E., 1992, “Wear Particle Formation in Lubricated Sliding Between a Hardened Sphere and a Flat Surface,” Tribology Ser. 21, Wear Particles: From the Cradle to the Grave, eds., D. Dowson et al., Elsevier, pp. 81–91.
15.
Magel, E. E., 1990, “Experimental and Theoretical Studies of the Wear of Heat Exchanger Tubes,” M.Sc. thesis, Dept. of Mech. Eng., University of British Columbia.
16.
Suh, N. P., 1981, “Update on the Delamination Theory of Wear,” Fundamentals of Friction and Wear of Materials, ed., D. A. Rigney, ASM, pp. 43–71.
17.
Taponat, M.-C, et al., 1995, “Etude experimentale de l’usure du contact tube de generateur de vapeur/barre anti-vibratoire—essais d’usure en eau pressurise´e sur le simulateur ERABLE 1,” EDF Report HT-22/94-31A.
18.
Taponat, M.-C, and Ko, P. L., 1993, “Etude de l’usure des tubes et des barres anti-vibratoires dans les ge´ne´rateurs de vapeur des centrales nucle´aires,” Parte 1, NRC Report IMR-TM-CTR-001, and Parte 2, NRC Report IMR-TM-CTR-009.
19.
Taponat, M.-C, and Ko, P. L., 1993, “Etude de l’usure des tubes et des barres anti-vibratoires dans les ge´n´erateurs de vapeur des centrales nucle´aires-Essais en impact-glissement,” Parte 1 NRC Report IMR-TM-CTR-010, and 1995, Parte 2 NRC Report IMR-T&M-CTR-016.
20.
Technology for the ’90s, 1993, ed., M. K. Au-Yang, ASME Special Publ. No. 100347,0-7918-0684-7.
21.
Thomgren, J. T., 1970, “Predict Exchanger Tube Damage,” Hydrocarbon Processing, X, pp. 129–131.
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