The characteristic fuel cycle (FC) schemes for fusion and hybrid (fusion-fission) reactors are considered. The FC structures of the facilities that are under construction and of newly designed ones are analyzed. The FC architecture general features and specific ones of each facility are highlighted. Two simplified FC schemes are proposed, and a computer program for solving a system of differential equations and simulating the accumulation of fusion fuel component (tritium) in FC systems in a steady-state operation mode of the facilities has been developed. The obtained results are compared with published calculations for the DEMO, SABR, and DEMO-FNS facilities. The computer codes used for numerical simulation of the fusion reactor FCs are reviewed; a high relevance of the problem being solved is shown, and proposals for further sophistication of the developed model are formulated.

The characteristic fuel cycle (FC) schemes for fusion and hybrid (fusion-fission) reactors are considered. The FC structures of the facilities that are under construction and of newly designed ones are analyzed. The FC architecture general features and specific ones of each facility are highlighted. Two simplified FC schemes are proposed, and a computer program for solving a system of differential equations and simulating the accumulation of fusion fuel component (tritium) in FC systems in a steady-state operation mode of the facilities has been developed. The obtained results are compared with published calculations for the DEMO, SABR, and DEMO-FNS facilities. The computer codes used for numerical simulation of the fusion reactor FCs are reviewed; a high relevance of the problem being solved is shown, and proposals for further sophistication of the developed model are formulated.