Hybrid fission-fusion systems and statistical simulation of particle transport

Abstract

The article presents comparative analysis of characteristics of different hybrid systems: ADS systems, a neutron source system based on TOKAMAK and systems with a neutron source based on the open plasma traps. The focus is on the development of the latter ones, which are noted for technical simplicity, low-cost source and high utilization of neutrons. It is shown that the developed system of codes for the simulation of the plasma neutron source based on gas-dynamic trap (GDT), neutron transport, and isotope kinetics allows calculations to optimize various parameters of hybrid system, and obtain necessary characteristics to analyze the technical and economic efficiency of such systems.