Fretting-Wear Characteristics of Steam Generator Tubes by Foreign Object |
Jo Jong Chull
(Korea Institute of Nuclear Safety)
Jhung Myung Jo (Korea Institute of Nuclear Safety) Kim Woong Sik (Korea Institute of Nuclear Safety) Choi Young Hwan (Korea Institute of Nuclear Safety) Kim Hho Jung (Korea Institute of Nuclear Safety) Kim Tae Hyung (Korea Power Engineering Company, Inc.) |
1 | Archard, J. F., and Hirst, T., 1956, 'The Wear of Metals under Unlubricated Conditions,' Proceedings of the Royal Society of London, Vol.A(236), p.397 |
2 | Au-Yang, M. K., 2001, Flow-induced Vibration of Power and Process Plant Components, ASME Press, New York |
3 | Lindeburg, M. R., 1994, Mechanical Engineering Reference Manual, 9th ed., Professional Publications, Inc. |
4 | Singhal, A. K., and Srikantiah, G. S., 1991, 'A Review of Thermal Hydraulic Analysis Methodology for PWR Steam Generators and ATHOS3 Code Applications,' Progress in Nuclear Energy, Vol.25, No.1, pp.7-70 DOI ScienceOn |
5 | Jo, J. C. et al., 1992, A Study on the Thermal-hydraulic and Flow-induced Tube Vibration Analysis of Nuclear Steam Generators, KINS/AR-198, Korea Institute of Nuclear Safety, Daejeon, Korea |
6 | Pettigrew, M. J., and Taylor, C. E., 1994, 'Two-Phase Flow-Induced Vibration: An Overview,' ASME Journal of Pressure Vessel Technology, Vol.116, pp.233-253 ScienceOn |
7 | Keeton, L. W., and Singhal, A. K., 1986, ATHOS3 : A Computer Program for Thermal Hydraulic Analysis of Steam Generators, NP-4604-CCM, Electric Power Research Institute, Palo Alto, CA. |
8 | ANSYS, 2001, ANSYS Structural Analysis Guide, ANSYS, Inc., Houston |
9 | Connors, H. J., 1981, 'Flow-Induced Vibration and Wear of Steam Generator Tubes,' Nuclear Technology, Vol.55, pp.311-331 |
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