Abstract: In the present work, specifications of Ghana Research Reactor 1 (GHARR-1) were adopted for modelling purpose to mimic the MNSR generic design. To ensure consistency in simulated results, GHARR-1 was equally used to experimentally generate data on the inlet and outlet temperatures of the reactor core at varying coolant flow rates for later used to simulate initial conditions of the thermal hydraulic code. The numerical values of flow parameters as contained in GHARR-1 Safety Analysis Report (SAR) were used to further condition the code and also to validate the convergence at the output stage. The model utilized 90% enriched U-235 to produce neutron flux of up to 1x1012 cm-2s-1 at a corresponding thermal power output of 31 kW. The core coolant modelling and simulation wereachieved using Simulation of Turbulent flow in Arbitrary Regions Computational Continuum Mechanics C++ based (STAR CCM+) Computational Fluid Dynamics (CFD) code. The code successfully analyzed the progression of flow parameters from the inlet to the outlet of the reactor core. Thermal hydraulic studies of the reactor core coolant is necessary for safety of evaluation of a nuclear reactor.
Keywords: STAR-CCM+, CFD, GHARR-1, core coolant, flow rates, thermal flux, thermal power, MNSR.
Title: SIMULATION OF COOLANT REYNOLD’S NUMBER AND VELOCITY IN THE CORE OF MINIATURE NEUTRON SOURCE NUCLEAR REACTORS (MNSRs)
Author: Salihu M., Gambo A., Adamu J., Bala S. Abdulrahaman A, Ibrahim A
International Journal of Computer Science and Information Technology Research
ISSN 2348-1196 (print), ISSN 2348-120X (online)
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