DOI QR코드

DOI QR Code

Vibration Characteristics of Steam Generator U-tubes with Defect

결함을 가진 증기발생기 U-튜브의 진동특성

  • 조종철 (한국원자력안전기술원 규제기술연구부) ;
  • 정명조 (한국원자력안전기술원 원자력안전연구실) ;
  • 김웅식 (한국원자력안전기술원 규제기술연구부) ;
  • 김효정 (한국원자력안전기술원 규제기술연구부) ;
  • 김태형 (한국전력기술주식회사 구조해석분야)
  • Published : 2003.05.01

Abstract

This paper investigates the vibration characteristics of steam generator (SG) U-tubes with defect. The operating SG shell-side flow field conditions for determining the fluidelastic instability parameters such as added mass are obtained from three-dimensional SG flow calculation. Modal analyses are performed for the U-tubes either with axial or circumferential flaw with different sizes. Special emphases are on the effects of flaw orientation and size on the modal and instability characteristics of tubes, which are expressed in terms of the natural frequency, corresponding mode shape and stability ratio. Also, addressed is the effect of the internal pressure on the vibration characteristics of the tube.

Keywords

References

  1. Keeton, L. W. and Singhal. A. K., 1986, "ATHOS3 : A Computer Program for Thermal Hydraulic Analysis of steam Generators," EPRI Report NP-4604-CCM, Vols. 1-3.
  2. Jhung, M. J. and Jeong K. H., 2001, "Natural Vibration Analysis of Two Circular Plates Coupled with Bounded Fluid," 한국소음진동공학논문집, 제 11권, 제 9호, pp. 439-453.
  3. Chen, S. S. and Chung, H., 1976, "Design Guide for Calculating Hydrodynamic Mass, Part 1 : Circular Cylindrical Structures," ANL Report ANL-CT-76-45, Argonne, IL.
  4. Pettigrew, M. J., Taylor, C. E. and Kim, B. S., 1989, "Vibration of Tube Bundles in Two-phase Cross-flow: Part 1 Hydrodynamic Mass and Damping," ASME Journal of Pressure Vessel Technology, Vol. III, pp. 466-477.
  5. Pettigrew, M. J., Rogers, R. J. and Axisa, F., 1986, "Damping of Multi-span Heat Exchanger Tubes, Part 2 : In Liquids," ASME Publication PVP-Vol. 104, New York.
  6. Pettigrew, M. J., Carlucci, L. N., Taylor, C. E. and Fisher, N. J., 1991, "Flow-induced Vibration and Related Technologies in Nuclear Components," Nuclear Engineering and Design, Vol. 131, pp. 81-100. https://doi.org/10.1016/0029-5493(91)90319-D
  7. ANSYS, 2001, ANSYS Structural Analysis Guide, ANSYS, Inc., Houston.
  8. Corners, H. J., 1981, "Flow-induced Vibration and Wear of Steam Generator Tubes," Nuclear Technology, Vol. 55, pp. 311-331.
  9. Eisinger, F. L., Rao, M. S. M. and Steininger, D. A., 1989, "Numerical Simulation of Fluidelastic Instability of Multispan Tubes Partially Exposed to Crossflow," SMiRT-10, Vol. T, pp. 45-57.
  10. Eisinger, F. L. and Juliano, T. M., 1975, "Flow-induced Vibration Analysis of Recuperator Tube Bank," Foster Wheeler Energy Corp. Report 156-MA-75-48.

Cited by

  1. Fretting-wear Characteristics of Steam Generator Helical Tubes vol.14, pp.4, 2004, https://doi.org/10.5050/KSNVN.2004.14.4.327