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TECHNICAL PAPERS: Forced Convection

The Effect of Support Grid Features on Local, Single-Phase Heat Transfer Measurements in Rod Bundles

[+] Author and Article Information
Mary V. Holloway, Heather L. McClusky, Donald E. Beasley

Department of Mechanical Engineering, Clemson University, Clemson, SC 29634

Michael E. Conner

Westinghouse Nuclear Fuel, 5801 Bluff Road, Columbia, SC 29250

J. Heat Transfer 126(1), 43-53 (Mar 10, 2004) (11 pages) doi:10.1115/1.1643091 History: Received December 23, 2002; Revised October 03, 2003; Online March 10, 2004
Copyright © 2004 by ASME
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References

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Yang,  S. K., and Chung,  M. K., 1998, “Turbulent Flow Through Spacer Grids in Rod Bundles,” ASME J. Fluids Eng., 120, pp. 786–791.
Karoutas, Z., Gu, C. Y., and Scholin, B., 1995, “3-D Flow Analyses for Design of Nuclear Fuel Spacer,” Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7, 1 , pp. 3153–3174.
K. W.,  In, 2001, “Numerical Study of Coolant Mixing Caused by the Flow Deflectors in a Nuclear Fuel Bundle,” Nucl. Technol., 134, pp. 187–195.
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McClusky, H. L., Holloway, M. V., Conover, T. A., Beasley, D. E., Conner, M. E., and Smith, L. D., III, 2003, “Mapping of the Lateral Flow Field in Typical Subchannels of a Support Grid with Vanes,” ASME J. Fluids Eng., 125 (6), pp. 987–996.
Saffman, P. G., 1992, Vortex Dynamics, Cambridge University Press.
de Crecy,  F., 1994, “The Effect of Grid Assembly Mixing Vanes on Critical Heat Flux Values and Azimuthal Location in Fuel Assemblies,” Nucl. Eng. Des., 149, pp. 233–241.
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Chang,  F., and Dhir,  V. K., 1995, “Mechanisms of Heat Transfer Enhancement and Slow Decay of Swirl in Tubes Using Tangential Injection,” Int. J. Heat Fluid Flow, 16, pp. 78–87.
Figliola, R. S., and Beasley, D. E., 1998, Theory and Design for Mechanical Measurements, 3rd Edition, John Wiley & Sons.
Armfield, M. V., 2001, “Effects of Support Grid Design on Local, Single-Phase Turbulent Heat Transfer in Rod Bundles,” Master’s Thesis, Clemson University, Clemson, SC, USA.
Armfield, M. V., Langford, H. M., Beasley, D. E., and Conner, M. E., 2000, “Average Heat Transfer Coefficient Measurements in a Fuel Bundle: Method Development,” Proceedings of the ASME Heat Transfer Division, HTD-366-2, ASME International, New York, pp. 163–170.
Rehme,  K., 1976, “Pressure Drop of Spacer Grids in Smooth and Roughened Rod Bundles,” Nucl. Technol., 33, pp. 314–317.
Marek, J., and Rehme, K., 1979, “Heat Transfer in Smooth and Roughened Rod Bundles Near Spacer Grids,” Presented at the ASME Winter Annual Meeting Dec 2–7, 1979, pp. 163–170.
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Figures

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Schematic diagram of 5×5 rod bundle assembly
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Representative drawings of support grid designs for the following: (a) grids A, E, and G; (b) grid B; (c) grid C; and (d) grids D, F, and H.
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Typical rod bundle subchannel with split-vane pair
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Drawing of experimental facility
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Drawing of heated copper sensor
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Nusselt numbers for standard grids A and G ε=εs=0.20
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Nusselt numbers for standard grid E ε=εs=0.14
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Nusselt number normalized by hydrodynamically fully developed Nusselt number for standard grids A and G, ε=εs=0.20
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Nusselt number normalized by hydrodynamically fully developed Nusselt number for support grids with disk blockage, grids B and C, ReDh=28,000,εs=0.20
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Nusselt number normalized by hydrodynamically fully developed Nusselt number for grid F, εs=0.14,Kfeat/Kv=0.15
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Nusselt number normalized by hydrodynamically fully developed Nusselt number for grids D, F, H, ReDh=28,000
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Nusselt number normalized by hydrodynamically fully developed Nusselt number for grids D, F, H, ReDh=42,000
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Nusselt number normalized by hydrodynamically fully developed Nusselt number for grids A, B, C, and D, ReDh=28,000,εs=0.20

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