Fluidelastic Instability Characteristics of Helical Steam Generator Tubes

  • 발행 : 2004.08.01

초록

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.

키워드

참고문헌

  1. 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
  2. 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
  3. ANSYS, 2003, ANSYS Structural Analysis Guide, ANSYS, Inc., Houston
  4. Connors, H.J., 1981, 'Flow-Induced Vibration and Wear of Steam Generator Tubes,' Nuclear Technology, Vol.55, pp.311-331
  5. Au-Yang, M.K., 2001, Flow-Induced Vibration of Power and Process Plant Components, ASME Press, New York
  6. 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
  7. 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
  8. Paidoussis, M.P., 1983, 'A review of flow-induced vibrations in reactors and reactor components,' Nuclear Science Engineering, Vol.74, pp.31-60 https://doi.org/10.1016/0029-5493(83)90138-3
  9. 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
  10. 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
  11. 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
  12. 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