Symbiotic system of a fusion and a fission reactor with very simple fuel reprocessing

The paper discusses a symbiotic fusion and fission reactor system. The method is based on producing U-233 in the blanket of the fusion reactor from thorium which circulates as ThF4 in a mixture of sodium and beryllium fluoride melts. The U-233 produced in the blanket supplies a fission reactor and generates fuel for additional symbiotic installations. Electric power and breed fuel with a doubling time of 4-5 years are produced when the ratio of thermal capacities of the fusion and fission reactor is 1:11. The reprocessing system consists of removing U-233 from the salt circulating in the reactor blanket and removing xenon from the fuel salt of the molten-salt reactor. It is also noted that tritium is produced in the fission reactor, the fusion reactor blanket is almost clean, and in principle all the thorium in the fusion reactor blanket can be used to produce U-233.