Combined Neutronics Calculation of the Radiation Protection for a Nuclear Reactor with Heavy Liquid-Metal Coolant

Abstract

The problem of calculating a model of the radiation protection of a monoblock reactor, having a fast neutron spectrum and cooled by a eutectic lead-bismuth alloy, by a combined method using the CADIS methodology is examined. A deterministic calculation of the adjoint problem is performed by the method of characteristics, ensuring the smoothness of the solution. An algorithm for selecting the nodes of the weight window grid is presented for the many-group problem. The results of the neutron flux density distribution for the computational domain are described. A statistical error of 7% is obtained, confirming the methodological reliability of the spatial distribution of the neutron flux density in the Monte Carlo method.