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Numerical simulation and experimental study of quasi-periodic large-scale vortex structures in rod bundle lattices

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초록

Study of flow behavior within rod bundles has been an active topic. Surface modification technologies are important parts of the design of the fourth generation reactor, which can increase the strength of the secondary flow within the rod bundle lattices. Quasi-periodic large-scale vortex structure (QLVS) is introduced by arranging micro ribs on the surface of rod bundles, which enhanced the scale of the secondary flow between the rod bundle lattices. Using computational fluid dynamics (CFD) and water experiments, the flow field distribution and drag coefficient of the rod-bundle lattices are studied. The secondary flow between the micro-ribbed rod-bundle lattice is significantly enhanced compared to the standard rod-bundle lattice. The numerical simulation results agree well with the experimental results.

Abstract

Study of flow behavior within rod bundles has been an active topic. Surface modification technologies are important parts of the design of the fourth generation reactor, which can increase the strength of the secondary flow within the rod bundle lattices. Quasi-periodic large-scale vortex structure (QLVS) is introduced by arranging micro ribs on the surface of rod bundles, which enhanced the scale of the secondary flow between the rod bundle lattices. Using computational fluid dynamics (CFD) and water experiments, the flow field distribution and drag coefficient of the rod-bundle lattices are studied. The secondary flow between the micro-ribbed rod-bundle lattice is significantly enhanced compared to the standard rod-bundle lattice. The numerical simulation results agree well with the experimental results.

참고문헌 (26)

  1. B. H. Yan, "The thermal hydraulic phenomenon in tight lattice bundles : a review", Ann. Nucl. Energy, 126, pp.330~349 (2019)
  2. M. S. Guellouz, "Heat transfer in rod bundle subchannels with varying rod-wall proximity", Nucl. Eng. Des, 132(3), pp.351~366 (1992)
  3. T. Krauss, "Experimental investigation of turbulent transport of momentum and energy in a heated rod bundle", Nucl. Eng. Des, 180(3), pp.185~206 (1998)
  4. H. Ninokata, "Analysis of low Reynolds number turbulent flow phenomena in nuclear fuel pin subassemblies of tight lattice configuration", Nucl. Eng. Des, 239(5), pp.855~866 (2009)
  5. R. Gajapathy, "CFD investigation of helical wire-wrapped 7-pin fuel bundle and the challenges in modeling full scale 217 pin bundle", Nucl. Eng. Des, 237, pp.2332~2342 (2007)
  6. S. V. Moller, "Single-phase turbulent mixing in rod bundles", Exp. Therm. Fluid Sci, 5(1), pp.26~33 (1992)
  7. M. S. Guellouz, "The structure of turbulent flow in a rectangular channel containing a cylindrical rod. Part 1 : Reynolds-averaged measurements;Part 2 : phase-averaged measure-ments", Exp. Therm. Fluid Sci, 23, pp.59~91 (2000)
  8. D. S. Rowe, "Measurement of Turbulent Velocity, Intensity and Scale in Rod Bundle Flow Channels", pp.1973
  9. J. D. Hooper, "The Structure of Single-phase Turbulent Flows through Closely Spaced Rod Arrays", ~ (1983)
  10. J. D. Hooper, "Large-scale structural effects in developed turbulent flow through closely-spaced rod arrays", J. Fluid Mech, 145, pp.305~337 (1984)
  11. F. Baratto, "Measurements of frequencies and spatial correlations of coherent structures in rod bundle flows", Nucl. Eng. Des, 236(17), pp.830~1837 (2006)
  12. H. Y. Jeong, "A dominant geometrical parameter affecting the turbulent mixing rate in rod bundles", Int. J. Heat Mass Tran, 50(5, pp.6) (2007), 908~918
  13. B. H. Yan, "Periodic large scale vortex structure in rectangular channels with nonuniform wall roughness", J. Nuclear Eng. Design, 241(8), pp.2948~2955 (2011)
  14. P. Saha, "Investigation of coherent structures in a turbulent channel with built-in longitudinal vortex generators", Int. J. Heat Mass Tran, 104, pp.178~198 (2017)
  15. O. C. A. Nalín, "Development of a measurement technique for detailed flow characterization in fuel bundles", Nucl. Eng. Des, 340, pp.146~155 (2018)
  16. L. Meyer, "From discovery to recognition of periodic large scale vortices in rod bundles assource of natural mixing between subchannels – a review", Nucl. Eng. Des, 240, pp.1575~1588 (2010)
  17. H. G. Xiao, "The research on coherent structure in 7-rod bundle lattice", Ann. Nucl. Energy, 124, pp.39~48 (2019)
  18. Y. L. Chi, "Effect of gap width on turbulent mixing of parallel flow in a square channel with a cylindrical rod", Exp. Therm. Fluid Sci, 47, pp.98~107 (2013)
  19. C. Tae-Hyun, "A pressure drop model for spacer grids with and without flow mixing Vanes", J. Nucl. Sci. Technol (1998)
  20. S. Y. Ma, "Research on coherent structure in 4-rod bundle lattice based on CFD", Ann. Nucl. Energy (2022)
  21. K. Hu, "Detailed Examples of ANSYS ICEM CFD Engineering" (2014), Posts &Telecom Press
  22. B. H. Yan, "URANS simulation of the turbulent flow in a tight lattice : effect of the pitch to diameter ratio", Prog. Nucl. Energy, 53(4), pp.428~437 (2011)
  23. N.E. Todreas, "Nuclear System I: Thermal Hydraulic Fundamentals", pp.343~459 (1990), McGraw-Hill Companies, Inc
  24. A. Haider, "Drag coefficient and terminal velocity of spherical and nonspherical particles", Powder Technol, 58(1), pp.63~70 (1989)
  25. M. Khan, "Flow around a cube for Reynolds numbers between 500 and 55,000", Exp. Therm. Fluid Sci, 93, pp.257~271 (2018)
  26. Eddies, Stream, and Convergence Zones in Turbulent Flows, "J. Hunt", R. Centre for Turbulence Research, ~, pp.Report CTR-S88 (1988)

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