Simulation Modeling Analysis of Operational Temperature Modes for the Fuel Rods in the IRT-T Research Reactor

In this research, numerous initiatives are focused on the creation of object-oriented software complexes for power reactors. The modern stage of nuclear technology development necessitates an increase in safety justification requirements, emphasizing the need for enhanced design programs. This paper delves into the details of the Tomsk Research Reactor (IRT-T). To ensure safety and visualize fluid streamline and temperatures, a rigorous technique is employed, offering profiles for both short and long-term evaluations. The simulation of natural convection flow is conducted by utilizing the computational fluid dynamic (CFD) code ANSYS-FLUENT. The model used to investigate the long-term operation of the reactor is a modified 3D porous medium. The results indicate that it would be favorable to extend the maximum operating limit of the natural convection mode to 8MW.