Heat transfer characteristics of fuel assemblies for a high flux research reactor with a neutron trap are numerically investigated in this study. Single-phase turbulence flow is calculated by a commercial code, FLUENT, where the computational objective covers standard 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 hot assemblies. The results indicate that the cladding temperature is always lower than the saturation temperature in the calculated ranges. The temperature rise in the control fuel assembly is smaller than that of the standard fuel assembly. Additionally, the assembly with a hot spot is specially studied, and the safety of the research reactor is also approved.
Gong, D., Huang, S., Wang, G., & Wang, K. (2015). Heat Transfer Calculation on Plate-Type Fuel Assembly of High Flux Research Reactor. Science and Technology of Nuclear Installations, 2015. https://doi.org/10.1155/2015/198654