3D-MODEL OF A LOW-POWER THERMONUCLEAR REACTOR FOR ESTIMATION OF BLANKET NEUTRON CHARACTERISTICS
In recent years, academician E.P. Velikhov and his colleagues outlined their vision of solving the problem of fissile fuel production for thermal nuclear reactors in thermonuclear reactor blankets. It was shown in these articles that the amount of 233U required to operate a 3.2 GW (th) thermal reactor can be produced in a blanket of a 400 MW (th) fusion reactor. Most of the works devoted to the use of hybrid thermonuclear reactors (GTR) for the production of fissile material have been carried out based on the general fundamental nuclear properties of isotopes in their interaction with neutrons having different energies, without using adequate geometric models of reactors. In the present work, this gap is filled by the creation and description of a 3D-fusion reactor model that maximally reproduces the configuration and design of the reactor components and serves as a basic tool for analyzing the GTR neutron characteristics, primarily the production rate of fissile isotopes 233U (233U) and 239Pu.