Direct numerical simulation of the peripheral and the internal configuration of the model fuel assembly

Due to the active development of nuclear energy in the world and in Russia, more and more attention is paid to the issues of energy efficiency and safety of nuclear reactors. Despite the fact that most of the reactors operating today have already been well studied, some hydrodynamic questions related to the flow of the moderator along the fuel elements still remain open. In particular, this paper considers the equivalence of flow in the peripheral and internal regions of the fuel assembly.