[논문]Fluidelastic Instability Characteristics of Helical Steam Generator Tubes

Jo Jong Chull; Jhung Myung Jo; Kim Woong Sik; Choi Young Hwan; Kim Hho Jung

Fluidelastic Instability Characteristics of Helical Steam Generator Tubes 원문보기

Journal of the Korean Nuclear Society = 원자력학회지, v.36 no.4, 2004년, pp.364 - 373

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)

Abstract ▼ AI-Helper

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.

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문제 정의

(1), where the critical velocity is proportional to the square root of the total damping ratio. Therefore, a more accurate estimation of the total damping ratio needs to be made to predict flu서기astic in마ability.
This study investigates the fluidelastic instability characteristics of helical steam generator tubes. Modal analyses are performed by finite element modeling of the tubes, using various conditions.

가설 설정

For the tube to be fluidelastically stable, the stability ratio defined in Eq. (4) should be less than unity, which means that the gap velocity should be less than the critical velocity. Therefore, the allowable gap velocity is less than the minimum value of the critical velocity shown in Figs.

제안 방법

(1) and (4). Several supports are installed in the circumferential direction, and the effect of supports on the frequencies is investigated by comparing the frequencies between those tubes with supports with those tubes without supports. Support points each turn are 2, 3, 4, 8 and 16 in the circumferential direction.
Modal analyses are performed by finite element modeling of the tubes, using various conditions. This investigation examines the effects of the number of turns, the number of supports, and the status of inner fluid on the modal and fluidelastic instability characteristics of tubes, which are expressed in terms of the natural frequency, corresponding mode shape, and stability ratio.
To investigate the vibration characteristics of a helical tube, modal analyses for various conditions, such as the status of inner fluid, the number of turns, and the number of supports were performed. The effects of the modal characteristics on fluidelastic instability were addressed.

대상 데이터

The element is capable of supporting only compression in the direction normal to the surfaces and shear (Coulomb friction) in the tangential direction. The finite element model consi아s of 1280 PIPE 16 elements for the helical tube and 65 CONTAC₅₂ elements between the support and the tube for 8 support points of Type A, as shown in Fig. 1.

이론/모형

The Block Lanczos method is used for the eigenvalue and eigenvector extractions to calculate 50 natural frequencies. It uses the Lanczos algorithm, where the' Lanczos recursion is performed with a block of vectors. This method is as accurate as the subspace method, but faster.

참고문헌 (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

원문보기 상세보기
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

원문보기 상세보기
ANSYS, 2003, ANSYS Structural Analysis Guide, ANSYS, Inc., Houston
Connors, H.J., 1981, 'Flow-Induced Vibration and Wear of Steam Generator Tubes,' Nuclear Technology, Vol.55, pp.311-331

상세보기
Au-Yang, M.K., 2001, Flow-Induced Vibration of Power and Process Plant Components, ASME Press, New York
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
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
Paidoussis, M.P., 1983, 'A review of flow-induced vibrations in reactors and reactor components,' Nuclear Science Engineering, Vol.74, pp.31-60

상세보기
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
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
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
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

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