Browse > Article

Fluidelastic Instability Characteristics of Helical Steam Generator Tubes  

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)
Publication Information
Nuclear Engineering and Technology / v.36, no.4, 2004 , pp. 364-373 More about this Journal
Abstract
This study investigates the fluidelastic instability characteristics of helical steam generator type tubes used in operating nuclear power plants. To obtain a natural frequency, corresponding mode shape, and participation factor, modal analyses using various conditions are performed for helical type tubes. Investigated are the effects of the number of turns, the number of supports, and the status of the inner fluid on the modal and fluidelastic instability characteristics of the tubes, which are expressed in terms of the natural frequency, the corresponding mode shape, and the stability ratio.
Keywords
fluidelastic instability; steam generator helical tubes; modal analyses; mode shape; participation factor; stability ratio;
Citations & Related Records
Times Cited By KSCI : 2  (Citation Analysis)
연도 인용수 순위
1 Cioncolini, A, Cammi, L., Castelli, G., Lombardi, C., Luzzi, L., Ricotti, M.E., 2003, 'Thermal Hydraulic Analysis of IRIS Reactor Coiled Tube Steam Generator,' Nuclear Mathematical and Computational Science : A Century in Review, American Nuclear Society
2 Eisinger, F.L., Rao, M.S.M., and Steininger, D.A., 1989, 'Numerical Simulation of Fluidelastic Instability of Multispan Tubes Partially Exposed to Cross Flow,' Proceedings of the 10th International Conference on Structural Mechanics in Reactor Technology, Vol.T, pp.45-57
3 Eisinger, F.L., and Juliano, T.M., 1975, Flow-Induced Vibration Analysis of Recuperator Tube Bank, 156-MA-75-48, Foster Wheeler Energy Corp., New Jersey
4 Yetisir, M, and Pettigrew, M.J., 2001, 'A simple approach to estimate fretting-wear damage in heat exchanger tubes ; verification and validation,' PVP-Vol.420.1, pp.7-16
5 Pettigrew, M.J., and Gorman, D.J., 1981, 'Vibration of heat exchanger tube bundles in liquid and two-phase cross-flow,' Flow-Induced Vibration Design Guidelines, The American Society of Mechanical Engineers, New York, pp.89-110
6 Jo, J.C., Jhung, M.J., Kim, W.S., Kim, H.J., and Kim, T.H., 2003, 'Vibration characteristics of steam generator U-tubes with defect,' Transactions of the Korean Society of Noise and Vibration Engineering, Vol.13, No.5, pp.400-408   과학기술학회마을
7 Paidoussis, M.P., 1983, 'A review of flow-induced vibrations in reactors and reactor components,' Nuclear Science Engineering, Vol.74, pp.31-60   DOI   ScienceOn
8 Connors, H.J., 1981, 'Flow-Induced Vibration and Wear of Steam Generator Tubes,' Nuclear Technology, Vol.55, pp.311-331
9 Au-Yang, M.K., 2001, Flow-Induced Vibration of Power and Process Plant Components, ASME Press, New York
10 ASME, 1998, Flow-Induced Vibration of Tubes and Tube Banks, ASME Boiler and Pressure Vessel Code, Section III, Appendix N-1300, The American Society of Mechanical Engineers, New York
11 ANSYS, 2003, ANSYS Structural Analysis Guide, ANSYS, Inc., Houston
12 Jo, J.C., Jhung, M.J., Kim, W.S., Choi, Y.H., Kim, H.J., and Kim, T.H., 2003, 'Fretting-wear characteristics of steam generator tubes by foreign object,' Journal of the Korean Nuclear Society, Vol.35, No.5, pp.442-453   과학기술학회마을