The Problem of Modeling the Geometry of Twisted Fuel Rods with X-Type Cross Section in the Performance of Thermohydraulic Calculations

Abstract

For creating computational models of processes affecting the safety of nuclear facilities, in accordance with the federal rules and regulations in the field of atomic energy use, the selected modeling methods, as well as the accepted approximations and assumptions shall be justified. The paper considers the issues of taking into account the specifics of modeling the geometry of twisted fuel rods with x-type cross section using nodalization software, as well as possible approaches to describing the geometry of such fuel rods during thermohydraulic calculations. The paper defines a preferred method for specifying geometry, which allows to correctly take into account the maximum value of the heat flux from the surface of the twisted fuel rods with x-type cross section when calculating temperatures in the core and the possibility of a heat exchange crisis on the surface of such fuel rods in case of violations of normal operation.