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Simulations of fluidelastic forces and fretting wear in U-bend tube bundles of steam generators: Effect of tube-support conditions

  • Hassan, Marwan (School of Engineering, University of Guelph) ;
  • Mohany, Atef (Department of Mechanical Engineering, University of Ontario Institute of Technology)
  • 투고 : 2014.05.30
  • 심사 : 2014.08.20
  • 발행 : 2016.08.25

초록

The structural integrity of tube bundles represents a major concern when dealing with high risk industries, such as nuclear steam generators, where the rupture of a tube or tubes will lead to the undesired mixing of the primary and secondary fluids. Flow-induced vibration is one of the major concerns that could compromise the structural integrity. The vibration is caused by fluid flow excitation. While there are several excitation mechanisms that could contribute to these vibrations, fluidelastic instability is generally regarded as the most severe. When this mechanism prevails, it could cause serious damage to tube arrays in a very short period of time. The tubes are therefore stiffened by means of supports to avoid these vibrations. To accommodate the thermal expansion of the tube, as well as to facilitate the installation of these tube bundles, clearances are allowed between the tubes and their supports. Progressive tube wear and chemical cleaning gradually increases the clearances between the tubes and their supports, which can lead to more frequent and severe tube/support impact and rubbing. These increased impacts can lead to tube damage due to fatigue and/or wear at the support locations. This paper presents simulations of a loosely supported multi-span U-bend tube subjected to turbulence and fluidelastic instability forces. The mathematical model for the loosely-supported tubes and the fluidelastic instability model is presented. The model is then utilized to simulate the nonlinear response of a U-bend tube with flat bar supports subjected to cross-flow. The effect of the support clearance as well as the support offset are investigated. Special attention is given to the tube/support interaction parameters that affect wear, such as impact and normal work rate.

키워드

과제정보

연구 과제 주관 기관 : Natural Science Foundation

참고문헌

  1. Anderson, B., Hassan, M. and Mohany, A. (2014), "Modelling of fluidelastic instability in a square inline tube array including the boundary layer effect", J. Fluid. Struct., 48, 362-375. https://doi.org/10.1016/j.jfluidstructs.2014.03.003
  2. El Bouzidi, S. and Hassan, M. (2015), "An investigation of time lag causing fluidelastic instability in tube arrays", J. Fluid. Struct., 57, 264-276. https://doi.org/10.1016/j.jfluidstructs.2015.06.005
  3. Granger, S. and Paidoussis, M.P. (1996), "An improvement to the quasi-steady model with application to cross-flow-induced vibration of tube array", J. Fluid Mech., 320, 163-184. https://doi.org/10.1017/S0022112096007495
  4. Hassan, M. and Mohany, A. (2013), "Fluidelastic instability modelling of loosely supported multi-span u-tubes in nuclear steam generators", J. Press. Vessel Technol. - ASME , 135, 011306.
  5. Hassan, M. and Rogers, R. (2005), "Friction modelling of preloaded tube contact dynamics", Nuclear Eng. Des., 235, 2349-2357. https://doi.org/10.1016/j.nucengdes.2005.05.004
  6. Hassan, M., Gerber, A. and Omar, H. (2010), "Numerical estimation of fluidelastic instability in tube arrays", J. Press. Vessel Technol. - ASME, 132 (4), 041307. https://doi.org/10.1115/1.4002112
  7. Hassan, M.A., Rogers, R.J. and Gerber, A.G. (2011), "Damping-controlled fluidelastic instability forces in multi-span tubes with loose supports", Nuclear Eng. Des., 241(8), 2666-2673. https://doi.org/10.1016/j.nucengdes.2011.05.028
  8. Lever, J.H. and Weaver, D.S. (1982), "A theoretical model for the fluidelastic instability in heat exchanger tube bundles", J. Press. Vessel Technol. - ASME, 104, 104-147.
  9. Lever, J. and Weaver, D. (1986), "On the stability of heat exchanger tube bundles, part ii: Numerical results and comparison with experiments", J. Sound Vib., 107(3), 393-410 https://doi.org/10.1016/S0022-460X(86)80115-8
  10. Mohany, A. Janzen, V., Feenstra, P. and King, S. (2012), "Experimental and numerical characterization of flow-induced vibration of multi-span U-tubes", J. Press. Vessel Technol. - ASME, 134, 011301. https://doi.org/10.1115/1.4004796
  11. Oengoren, A. and Ziada, S. (1998), "An in-depth study of vortex shedding, acoustic resonance and turbulent forces in normal triangle tube arrays", J. Fluid. Struct., 12, 717-758. https://doi.org/10.1006/jfls.1998.0162
  12. Price, S.J. (1995), "A review of theoretical models for fluidelastic instability of cylinder arrays in cross-flow", J. Fluid. Struct., 9, 463-518. https://doi.org/10.1006/jfls.1995.1028
  13. Paidoussis, M. (1983), "A review of flow-induced vibrations in reactors and reactor components", Nuclear Eng. Desi., 74(1), 31-60. https://doi.org/10.1016/0029-5493(83)90138-3
  14. Weaver, D. and Fitzpatrick, J. (1988), "A review of crossflow induced vibrations in heat exchanger tube arrays", J. Fluid. Struct., 2, 73-93. https://doi.org/10.1016/S0889-9746(88)90137-5

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