Conceptual Design and Analysis of CFETR TF Coil

摘要

China Fusion Engineering Test Reactor (CFETR) based on the Tokamak approach with superconducting magnet technology is envisioned to provide 50-200 MW fusion power and operate with a goal of an annual duty factor of 0.3-0.5. The reactor has the equivalent scale compared with ITER. The design of CFETR superconducting magnets is based on the magnet technology of ITER. The TF coils of CFETR are winded with Nb3Sn cable-in-conduit conductor (CICC). The pure tension theory is used in the design of TF coil. This paper describes the design and presents the critical engineering parameters of CFETR TF coil.