Thermal hydraulic analysis of supercritical water reactor cooled by TiO2 nanofluid
- 3 February 2019
- journal article
- research article
- Published by Taylor & Francis Ltd in Journal of Nuclear Science and Technology
- Vol. 56 (3), 291-299
- https://doi.org/10.1080/00223131.2019.1571452
Abstract
Heat transfer study of nanofluids as coolant in SCWRs core has been performed at Helwan University. A thermal hydraulic code has been produced to study the effect of TiO2 nanofluid water based as a coolant with comparison with pure water as a coolant. Various volume fractions of nanoparticles TiO2 (2, 6 and 10%) were used in order to investigate its effects on reactor thermalhydraulic characteristics. Based on Parameters of a SCW Canadian Deuterium Uranium nuclear reactor (CANDU), the fuel assembly was modeled to study the effect of nanoparticles volume fraction on thermos-physical properties of basic fluid and the temperature distribution of fuel, cladding surface and coolant in axial direction. The theoretical results showed that the density, viscosity and thermal conductivity of the coolant increases with the increase of nanoparticles volume fraction, contrasting to specific heat, which decreases with the increase in nanoparticles volume fraction.Keywords
This publication has 15 references indexed in Scilit:
- Effect Analysis of Volume Fraction of Nanofluid Al2O3-Water on Natural Convection Heat Transfer Coefficient in Small Modular ReactorWorld Journal of Nuclear Science and Technology, 2016
- Experimental study of heat transfer and flow resistance of supercritical pressure water in a SCWR sub-channelThe Journal of Supercritical Fluids, 2015
- Development and assessment of a sub-channel code applicable for trans-critical transient of SCWRNuclear Engineering and Design, 2013
- Thermal–hydraulic modeling of nanofluids as the coolant in VVER-1000 reactor core by the porous media approachAnnals of Nuclear Energy, 2013
- Nucleate Pool Boiling Heat Transfer Correlation for TiO2-Water NanofluidsJournal of ASTM International, 2012
- Empirical correlations to predict thermophysical and heat transfer characteristics of nanofluidsThermal Science, 2008
- Heat transfer properties of nanoparticle-in-fluid dispersions (nanofluids) in laminar flowInternational Journal of Heat and Mass Transfer, 2005
- Heat transfer to supercritical fluids flowing in channels—empirical correlations (survey)Nuclear Engineering and Design, 2004
- Supercritical-pressure, Once-through Cycle Light Water Cooled Reactor ConceptJournal of Nuclear Science and Technology, 2001
- Thermal Conductivity of Nanoparticle - Fluid MixtureJournal of Thermophysics and Heat Transfer, 1999