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Flow-Induced Vibration Test in the Preheater Region of a Steam Generator Tube Bundle

Kim, Beom-Shig  
  • 초록

    Cross-flow existing in a shell-and-tube steam generator can cause a tube to vibrate. There are four regions subjected to cross-flow in Yonggwang units 3 and 4 (YGN 3 and 4) steam generators, which are of the same design as the steam generators for Palo Verde nuclear power plant Palo Verde units 1 and 2 steam generators have experienced localized oar at the comers of the cold side recirculating fluid inlet regions. A number of design modifications were made to preclude tube failure in specific regions of YGN 3 and 4 steam generators. Therefore, flow induced vibration experiments were done to determine the vibration magnitude of tubes in the economizer tube free lane region. The objective of this experiment is to demonstrate that the tube displacement is less than 0.01 inch rms at 100% of full power flow and to quantify the remaining design margin at 120ft and 140% of full power flow.


  • 참고문헌 (7)

    1. A Comparison of Degraded Tube Support Vibration Test Model Parameters Versus Millstone Ⅱ Steam Generator , B.T. Lubin;P.K. Shah;J.G. Thakkar , Combustion Engineering Report CENC-1785(Revision 3) / v.,pp.,
    2. Design Guide for Calculating Hydrodynamic Mass Part Ⅰ: Circular Cylinderical Structures , S.S. Chen;Ho. Chung , Argonne National Laboratory, Technical Memorandum, ANL-CT-76-45 / v.,pp.,
    3. Test Specification Flow Induced Tube Vibration Test Yonggwang Nuclear 3 and 4 Steam Generator Economizer and Lower Tube Bundle , N.L. Beard;D.E. Hart;J.K. Hayes;W.J. Heilker , ABB-CE Report CENC-1901(Revision 3) / v.3,pp.,
    4. Vibration of Heat Exchanger Components in Liquid and Two-Phase Cross-Flow , M.J. Petigrew;D.J. Gorman , Atomic Energy of Canada Limited Report AECL-6184 / v.,pp.,
    5. Vibration of Tube Bundles in Two-Phase Cross-Flow-Part 1 : Hydrodynamic Mass and Damping , M.J. Pettigrew;C.E. Taylor;B.S. Kim , ASME Journal of Pressure Vessel Technology / v.111,pp.466-477,
    6. Flow Induced Vibration Analysis in Support of the design of the Yonggwang Units 3 and 4 Steam Generator , W.J. Heilker;N.L. Beard;J.Y. Park , Proceedings of the International Symposium on Pressure Vessel Technology and Nuclear Codes and Standards / v.,pp.2-38-2-56,
    7. Damping of Multispan Heat Exchanger Tubes : Part 2;In Liquids , M.J. Pettigrew;R.J. Rogers;F. Axisa , ASME PVP / v.104,pp.,

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