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Efficient Heat Transfer Solution

 

Heat Transfer Enhancement in Nuclear Fuel rod bundles

It proposes to investigate the applicability of the roughening technique to enhance heat transfer in nuclear fuel bundles. The investigation involves experimental testing and numerical simulations. The experimental testing consists of Single Heater Element Loop Test (SHELT) constructed at USC. Observations will be made on differential pressure, velocity leodistribution, and temperatures for different roughness configurations. The numerical simulation involves Computational Fluid Dynamics (CFD) models of single and rod bundles to predict friction and heat transfer coefficients on the surface of the tube. The roughness design optimization will be performed during the CFD analyses, which utilize height, width, and pitch as design parameters. At least for the bi-dimensional parallel rib-type roughness, the CFD results are expected to be comparable to those obtained in previous work for gas-cooled and light-water reactors. The latter is described in the background review.

Related Publications:

  1. Leo A. Carrilho, Jamil Khan, Michael E. Conner, Abdel Mandour, Milorad B. Dzodzo, "TWO AND THREE-DIMENSIONAL SIMULATIONS OF ENHANCED HEAT
    TRANSFER IN NUCLEAR FUEL ROD BUNDLES", 2009 ASME Summer Heat Transfer Conference July 19-23, 2009, San Francisco, California, USA.

for more information : carrilla@westinghouse.com

Funded by : wh