증기발생기 세관용 Inconel 690 의 프레팅 마찰 및 마멸특성

Friction and Wear of Inconel 690 for Steam Generator Tube in Fretting

  • 이영제 (성균관대학교 기계공학부) ;
  • 임민규 (성균관대학교 대학원 기계공학부) ;
  • 오세두 (성균관대학교 대학원 기계공학부)
  • 발행 : 2003.03.01


Inconel 690 for nuclear steam generator tube has more Chromium than the conventionally used Inconel 600 in order to increase the corrosion resistance. To evaluate the tribological characteristics of Inconel 690 under fretting condition the fretting tests were carried out in air and elevated temperature water. 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. From the results of fretting wear tests. the wear of Inconel 690 can be predictable using the work rate model. The amounts of friction forces were proportional to relative movement between two fretting surfaces. The friction coefficients were decreased as increasing the normal loads and deceasing the vibrating amplitudes. Depending on fretting environment, distinctively different wear mechanisms and often drastically different wear rates can occur It was found that the fretting wearfactors in air and water at 2$0^{\circ}C$, 5$0^{\circ}C$, and 8$0^{\circ}C$ were 7.38 $\times$ $10^{-13}$$Pa^{-1}$, 2.12 $\times$$10^{-13}$$Pa^{-1}$, 3.34$\times$$10^{-13}$$Pa^{-1}$and 5.21$\times$$10^{-13}$$Pa^{-1}$, respectively flexibility to model response data with multiple local extreme. In this study, metamodeling techniques are adopted to carry out the shape optimization of a funnel of Cathode Ray Tube, which finds the shape minimizing the local maximum principal stress. Optimum designs using two metamodels are compared and proper metamodel is recommended based on this research.


프레팅 마찰;프레팅 마멸;인코넬 690;스틱-슬립


  1. Bowden, F.P. and Tabor, D., 1964, The Friction and Lubrication of Solids, Clarendon Press
  2. Rabinowicz, E., 1995, Friction and Wear of Materials, Wiley Publication, pp. 68-72
  3. Fisher, N.J., Chow, A.B., et al., 1995. 'Experimental Fretting- Wear Studies of Steam Generator Materials,' Journal of Pressure Vessel Technology' Vol. 117, pp. 312-320
  4. Taylor, C.E., Pettigrew, M.J., et al., 1998, 'Vibration Damping in Multispan Heat Exchanger Tubes,' Journal of Pressure Vessel Technology, Vol. 120, pp. 283-289
  5. Stachowiak, G.W. and Batchelor, A.W., 1993. Engineering Tribology, Elsevier, pp. 683-700
  6. Guerout. F.M. and Fisher, N.J., 1999, 'Steam Generator Fretting-Wear Damage : A Summary of Recent Findings,' Journal of Pressure Vessel Technology, Vol. 121, pp. 304-310
  7. Ko, P.L and Basista, H., 1984, 'Correlation of Support Impact Force and Fretting-Wear for a Heat Exchanger Tube.' Journal of pressure Vessel Technology, Vol. 106, pp. 69-77
  8. Ko, P.L.. 1985, 'Heat Exchanger Tube Fretting Wear: Reviews and Application to Design,' Journal of Tribology, Vol. 107, pp. 149-156
  9. Kang, S.C., Song, M.H., et al., 1999, Regulatory Technical Report on the Steam Generator Safety of Nuclear Power Plants, Korea Institute of Nuclear Safety, Report KINS/AR-669, pp. 5-37
  10. MacDonald. P.E., Shah, Y.N., et al., 1996, Steam Generator Tube Failure, U.S. Nuclear Regulatory Commission, Report NUREG/CR-6365. pp. 1-77
  11. Kim, D.G. and Lee, Y.Z., 2001, 'Experimental Investigation on Sliding and Fretting Wear of Steam Generator Tube Material,' WEAR, Vol. 250, pp. 673-680
  12. Miglin, B.P. and Sarver, J.M., 1991, 'Investigation of Lead as a Cause of Stress Corrosion Cracking at Support Plate Intersections,' Electric Power Research Institute, EPRI NP-7367-M