Mathematical Model of the Fast Neutrons Reactor with Pool Arrangement of Equipment

There was developed and described a 3D mathematical model (in X-Y-Z geometry) for the analysis of transient conjugate problems of convective heat transfer in the elements of the primary loop for the fast reactor with the integral equipment arrangement. Thermohydraulics of the core is described in the framework of the model of an anisotropic porous medium. To calculate the temperature profile in a fuel rod, in each computational cell of the core there is solved the 1D (with respect to radius of a fuel rod) equation of heat conduction at specified heat generation. Convection in the head chamber and in mixing chamber is described by the Navier-Stokes equations with effective turbulent viscosity and thermal conductivity. In mathematical modeling there is employed the generalized form of the governing equations which allows to describe thermal and convective phenomena both in the core and in the mixing chambers. This fact makes possible to construct homogeneous algorithms for solving conjugate convection/diffusion problems in the whole primary loop.