Engineering Physics Annotation << Back FUEL CYCLE OF A HYBRID REACTOR BASED ON TOKAMAK WITH DEUTERIUM PLASMA A.YU. CHIRKOV, D.E. FEDYUNIN The initial stage of industrial use of thermonuclear fusion associated with the problem of accumulating the required amount of tritium. The possibility of implementing a fuel cycle based on the D–D reaction with the production of tritium in deuterium plasma without its breeding in a blanket is considered. The parameters of fusion–fission hybrid with a neutron source based on a tokamak with a reduced aspect ratio are estimated. The limiting parameters of the tokamak are considered, which makes it possible to estimate the parameters for modes with acceptable effi ciency. It is shown that such systems can potentially produce tritium. Devices of relatively small sizes are also considered as prototypes of thermonuclear systems. The estimated parameters of reactors and prototypes show that in the case of a fuel cycle based on the D–D reaction, a demonstration neutron source for a hybrid system is only possible on a devices corresponding to a reactor scale. Keywords: deuterium, tritium, hybrid reactor, plasma, energy balance. DOI: 10.25791/infizik.10.2021.1232 Pp. 41-49.