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This is the second in a two-part series of papers on the behavior of nanofluids as a
PWR nuclear reactor coolant, where heat transfer enhancement is studied through
the use of homogeneous mixture of nanoparticles with water so called ?nanofluid? as
the reactor coolant. In the first paper we described the attribution of nanofluids to
the neutronic properties of a PWR System-80 reactor core. This paper investigates the
thermal hydraulic attribution of nanofluids as a coolant for the PWR NSSS (Nuclear
Steam Supply System).
A typical fuel assembly coolant channel of the PWR System 80 is modeled using
Computational Fluid Dynamic (CFD) code. The heat transfer coefficient, pressure
drops and temperature profiles are calculated for three types of nanofluids including
Al2O3, CuO and ZrO2. Among the nanofluids studied, Al2O3 is shown to have suitable
properties which enhances heat transfer coefficient in mass flux >4000 Kg⁄m2-s and
volume fraction of >5%.
Kamal Hadad has completed his Ph.D from University of Arizona, Department of Aerospace Mechanical
Engineering. He has published more than 100 papers in accredited journals and International
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