Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

Fluidelastic instability of a curved tube array in single phase cross flow

  • Kang-Hee Lee (Nuclear Fuel Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Heung-Seok Kang (Nuclear Fuel Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Du-Ho Hong (Doosan Heavy Industries & Construction) ;
  • Jong-In Kim (Doosan Heavy Industries & Construction)
  • Received : 2022.05.31
  • Accepted : 2022.11.12
  • Published : 2023.03.25
Download PDF
⟨ Previous Next ⟩

Abstract

Experimental study on the fluidelastic instability (FEI) of a curved tube bundle in single phase downward cross flow is investigated for the design qualification and analysis input preparation of helical coiled steam generator tubing. A 6×9 normal square curved tube array with equal and different vertical/horizontal pitch-to-diameter ratio was under-tested up to 6 m/s in term of gap flow velocity to measure the critical velocity for FEI. The critical velocity for FEI was measured at the turning point from the vibration amplitude plot along the gap flow velocity. Our test results were compared with straight tube results and published data in the design guideline. The applicability of the current design guidelines to a curved tube bundle is also assessed. We found that introducing frequency difference in a curved tube array increases the critical velocity for fluidelastic instability.

Keywords

Acknowledgement

This work has been carried out under the research funding contract from DHIC (N19039-160SS-0100) and SMR export commercialization technology development of KHNP.

References

  1. H.J. Connors, Fluidelastic vibration of tube Arrays excited by cross flow, in: D.D. Reiff (Ed.), Flow-Induced Vibrations in Heat Exchangers, ASME, New York, 1970, pp. 42-56.
  2. S.S. Chen, Guidelines for the instability flow velocity of tube arrays in cross flow, J. Sound Vibration 93 (1984) 439-455. https://doi.org/10.1016/0022-460X(84)90340-7
  3. M.K. Au-Yang, Flow-Induced Vibration of Power and Process Plant Components, ASME Press, New York, NY, 2001, p. 63~107.
  4. M. Pettigrew, C. Taylor, Vibration analysis of shell-and-tube heat exchangers: an overview-Part 1: flow, damping, fluidelastic instability, J. Fluids Structur. 18 (2003) 469-483. https://doi.org/10.1016/j.jfluidstructs.2003.08.007
  5. M.J. Pettigrew *, C.E. Taylor, N.J. Fisher, M. Yetisir, B.A.W. Smith, Flow-induced vibration: recent findings and open questions, Nuclear Eng. Design 185 (1995) 249-276. https://doi.org/10.1016/S0029-5493(98)00238-6
  6. D.S. Weaver, J.A. Fitzpatric, A review of cross-flow induced vibrations in heat exchanger tube arrays, J. Fluids Structur. 2 (1988) 73-93, 1988. https://doi.org/10.1016/S0889-9746(88)90137-5
  7. S.J. Price, A review of theoretical models for fluidelastic instability of cylinder arrays in cross-flow, J. Fluids Structur. 9 (1995) 463-518, 1995. https://doi.org/10.1006/jfls.1995.1028
  8. M.D. Blevins, Flow-Induced Vibration, second ed., Van Nostrand Reinhold, 1990.
  9. S.S. Chen, Flow-induced Vibration of Circular Cylindrical Structures, Hemisphere publishing corporation, New York, 1987, pp. 386-434.
  10. M.J. Pettigrew, C. E Taylor, N.J. Fisher, Flow-induced Vibration Handbook for Nuclear and Process Equipment, published by ASME Press and John Wiley & Sons, Inc., 2021, pp. 183-266.
  11. M.K. Au-Yang, R.D. Blevins, T.M. Mulcahy, Flow-induced vibration analysis of tube bundles - a proposed section III appendix N nonmandatory code, J. Pressure Vessel Technol. 113 (1991) 257-267. https://doi.org/10.1115/1.2928753
  12. Appendices N-1300, ASME Section III Division I, Flow-Induced Vibration of Tubes and Tube Banks, 2007.
  13. S.H. Lee, K. Kim, H.J. Kim, Y.S. Eun, Analysis of SGTR accident with Mihama unit experience, J. Korean Nuclear Soc. 26 (1) (1994). March 1994.
  14. R.D. Blevins, Nonproprietary flow-induced vibration analysis of san onofre nuclear generating station replacement steam generators to ASME code section III appendix N, J. Pressure Vessel Technol. 140 (2018), 034502-1~5. https://doi.org/10.1115/1.4039391
  15. S.C. E, San Onofre Nuclear Generating Station Unit 2 Return to Service Report, Southern California Edison, Rosemead, CA, 2013. Technical Docket No. 50-361.