Effects of Spacer Grid on Thermal-Hydraulic Performance of Fluid in a 4×4 Fuel Channel of VVER-1200 by using Ansys Fluent

In this paper, the structural design of a spacer grid of VVER-1200 has been done by Fusion 360 software. Simulation has been done using Ansys fluent software of temperature profile, velocity profile, and pressure drop along the flow path of fuel assembly to find out the optimum spacing between two spacer grids in a reactor core. Proper spacing between spacer grids helps maintain an optimal coolant, temperature, velocity, and pressure drop ensuring efficient heat removal. This, in turn, contributes to the overall efficiency of the nuclear reactor and generates green energy. The convective heat transfer rate from the fuel rods to the coolant is a crucial factor in determining the total power generation of a nuclear reactor. The resulting impact on heat transfer efficiency directly influences the total power production of the reactor. In general, one of the most important aspects of nuclear power reactor performance is the distribution of temperature, velocity, and pressure along a sub-channel with a spacer grid. To increase heat transfer and turbulent flow, which can raise the reactor's power efficiency, the spacer grid structure is necessary. The distribution of temperature, pressure, and velocity along a sub-channel with a spacer grid is a critical factor that optimizes the circumstances for efficient heat transfer, as may be inferred from the result. The modeling of 4x4 fuel rod assemblies and the prediction of temperature, pressure drop, and velocity distribution along the coolant flow direction have both been accomplished with success using the Ansys Fluent program. Additionally, various PWR-based nuclear power reactor subchannels can use this process.