Numerical simulation of the fluid flow and heat transfer of the supercritical water in the 64-element Canadian SCWR fuel bundle
- 21 March 2023
- journal article
- research article
- Published by Taylor & Francis Ltd in Journal of Nuclear Science and Technology
- Vol. 60 (10), 1228-1243
- https://doi.org/10.1080/00223131.2023.2188269
Abstract
Canada has participated in the Generation IV nuclear energy systems focusing on the Supercritical Water-cooled Reactor (SCWR) system. The 64-element fuel rods channel is used in the Canadian SCWR. There are few publicly available experimental studies for the flow in the fuel channels with multiple fuel rods. To date, the CFD simulation reported in open literature for rod bundle flow in the 64-element SCWR is relatively scarce. The cladding surface temperature is of key importance in assessing the safety of the reactor. Since the inhomogeneities in the bundle cross-section can present complex flow phenomena, a CFD study can provide substantial insight into the flow physics. In this work, the full-scale CFD simulation of the supercritical water flow in the 64-element rod bundle was performed. The results suggest the possibility of the presence of gap vortices in the flow subchannels. Higher streamwise velocities and normal Reynolds stresses always exist at the center subchannel regions. The circumferential cladding surface temperature distribution is extremely non-uniform and there is a large difference between the maximum cladding surface temperatures for different fuel rods. Graphical AbstractFunding Information
- Natural Sciences and Engineering Research Council of Canada (#04757)
This publication has 36 references indexed in Scilit:
- Rod bundle vortex networks, gap vortex streets, and gap instability: A nomenclature and some comments on available methodologiesNuclear Engineering and Design, 2011
- Numerical Simulation of Fluid Flow and Heat Transfer of Supercritical Fluids in Fuel BundlesJournal of Nuclear Science and Technology, 2011
- Numerical Simulation of Heat Transfer of Supercritical Fluids in Circular Tubes Using Different Turbulence ModelsJournal of Nuclear Science and Technology, 2011
- Numerical study on flow and heat transfer characteristics in the rod bundle channels under super critical pressure conditionAnnals of Nuclear Energy, 2010
- Numerical simulation of heat transfer deterioration phenomenon in supercritical water through vertical tubeAnnals of Nuclear Energy, 2010
- Numerical analysis of supercritical water heat transfer in horizontal circular tubeProgress in Nuclear Energy, 2010
- Anisotropic Turbulence and Coherent Structures in Eccentric Annular ChannelsFlow, Turbulence and Combustion, 2008
- Two-equation eddy-viscosity turbulence models for engineering applicationsAIAA Journal, 1994
- Forced convective heat transfer to supercritical water flowing in tubesInternational Journal of Heat and Mass Transfer, 1972
- The prediction of laminarization with a two-equation model of turbulenceInternational Journal of Heat and Mass Transfer, 1972