Browse > Article

Fretting Wear and Friction of lnconel 690 for Steam Generator Tube in Elevated Temperature Water  

Lee, Young-Ze (School of Mechanical Engineering, Sungkuunkwan University)
Lim, Min-Kyu (School of Mechanical Engineering, Sungkuunkwan University)
Oh, Se-Doo (School of Mechanical Engineering, Sungkuunkwan University)
Publication Information
KSTLE International Journal / v.3, no.1, 2002 , pp. 49-53 More about this Journal
Abstract
Inconel 690 for nuclear steam generator tube has more chromium than the conventionally used Inconel 600 in order to increase the corrosion resistance. TD evaluate the tribological characteristics under fretting condition the fretting tests as well as sliding tests were carried out in elevated temperature water environment. Fretting tests of the cross-cylinder type were done under various vibrating amplitudes and applied normal loads in order to measure the friction forces and wear volumes. Also, the conventional sliding tests of pin-en-disk type were carried out to compare the test results. In fretting, the friction was very sensitive to the load and the amplitude. The friction coefficient decreased with increasing load and decreasing amplitude. Also, the wear of Inconel 690 can be predictable using the work rate model. Depending on normal loads and vibrating amplitudes, distinctively different wear mechanisms and of ten drastically different wear rates can occur. It was fecund that the fretting wear coefficients in water were increased as increasing the temperature of water.
Keywords
Fretting wear; sliding wear; Inconel 690; work rate model; stick-slip;
Citations & Related Records
연도 인용수 순위
  • Reference
1 Tayor, C. E. and Pettigrew, M. J. et al., 'Vibration Damping in Multi-span Heat Exchanger Tubes,' J. of Pressure VesselTechnology, Vol. 120, pp. 283-289, 1998   DOI   ScienceOn
2 Ko, P. L. and Basista, H., 'Correlation of Support Impact Force and Fretting-Wear for a Heat Exchanger Tube,' J. of Pressure Vessel Technology, Vol. 106, pp. 69-77, 1984   DOI
3 Fisher, N. J. and Chow, A. B. et al., 'Expehmental FrettingWear Studies of Steam Generator Materials,' J. of Pressure Vessel Technology, Vol. 117, pp. 312-320, 1995   DOI
4 Ko, P. L. and Taponat, M. C. et al., 'Wear Studies of Materials for Tubes and Anti-vibration Bars in Nuclear Steam Generators,' J. of Pressure Vessel Technology, Vol. 118, pp. 287-300, 1996   DOI   ScienceOn
5 Guerout, F. M. and Fisher, N. J., 'Steam Generator FrettingWear Damage: A Summary of Recent Findings,' J. of Pressure Vessel Technology, Vol. 121, pp. 304-310, 1999   DOI