Heat transfer characteristics of fuel assemblies for a high flux research reactor with a neutron trap are numerically investigated in\nthis study. Single-phase turbulence flow is calculated by a commercial code, FLUENT, where the computational objective covers\nstandard and control fuel assemblies. The simulation is carried out with an inlet coolant velocity varying from 4.5 m/s to 7.5 m/s in\nhot assemblies. The results indicate that the cladding temperature is always lower than the saturation temperature in the calculated\nranges.The temperature rise in the control fuel assembly is smaller than that of the standard fuel assembly.Additionally, the assembly\nwith a hot spot is specially studied, and the safety of the research reactor is also approved.
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