Axial temperature distribution in the subchannel of a PWR based on two approaches

analytical and numerical

Abstract

In a nuclear reactor core, the heat generated by nuclear fission in the fuel is removed by a cooling fluid. While heat transfer must be optimized to increase process efficiency, the temperature in the core must not exceed certain safety limits, making thermal analysis of fuel elements the subject of various investigations, both in their design and operation. Different ways to model this type of problem are possible. In this work, an analytical approach through the energy balance in the subchannel and a numerical approach using the Finite Volume Method were studied. The results obtained were compatible, which indicated the validity of the developed numerical model, providing greater reliability to other analyses that can be made based on the simulation performed.