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

Author:

Holloway Mary V.1,McClusky Heather L.1,Beasley Donald E.1,Conner Michael E.2

Affiliation:

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

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

Abstract

Locally averaged heat transfer measurements in a rod bundle downstream of support grids with and without flow-enhancing features are investigated for Reynolds numbers of 28,000 and 42,000. Support grids with disk blockage flow-enhancing features and support grids with split-vane pair flow enhancing features are examined. Grid pressure loss coefficients and feature loss coefficients are determined based on pressure drop measurements for each support grid design. Results indicate the greatest heat transfer enhancement downstream of the support grid designs with disk blockages. In addition, the local heat transfer measurements downstream of the split-vane pair grid designs indicate a region of decreased heat transfer below that of the hydrodynamically fully developed value. This decreased region of heat transfer is more pronounced for the lower Reynolds number case. A correlation for the local Nusselt numbers downstream of the standard support grid designs is developed based on the blockage of the support grid. In addition, a correlation for the local Nusselt numbers downstream of support grids with flow-enhancing features is developed based on the blockage ratio of the grid straps and the normalized feature loss coefficients of the support grid designs. The correlations demonstrate the tradeoff between initial heat transfer enhancement downstream of the support grid and the pressure drop created by the support grid.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Condensed Matter Physics,General Materials Science

Reference25 articles.

1. Rehme, K. , 1973, “Pressure Drop Correlations for Fuel Element Spacers,” Nucl. Technol., 17, pp. 15–23.

2. Herer, C., 1991, “3D Flow Measurements in Nuclear Fuel Rod Bundles Using Laser Doppler Velocimetry,” ASME Fluid Measurement and Instrumentation Forum, 108, ASME International, New York, pp. 95–99.

3. Yang, S. K., and Chung, M. K., 1998, “Turbulent Flow Through Spacer Grids in Rod Bundles,” ASME J. Fluids Eng., 120, pp. 786–791.

4. 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.

5. In, K. W. , 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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