Physics Design of CFETR: Determination of the Device Engineering Parameters

Chinese Fusion Engineering Test Reactor (CFETR) based on the tokamak approach with superconducting magnet technology is envisioned to provide 200-MW fusion power and operate with a goal of an annual duty factor of 0.3-0.5. This report based on a zero-dimensional system study using extrapolations of current physics by considering engineering constraints, is focused on qualitative determination of the engineering parameters of the device. Conservative assumptions of plasma performance based on present day existing experiments were made to assure achievable goals, since CFETR could be a near-term project to bridge the gaps between ITER and DEMO. The baseline of 200-MW fusion power in standard H-mode for a duration longer than 1000 s and in a modest improved H-mode (or hybrid mode) with H-98 <= 1.3 for steady-state operation derive a device of R = 5.7 m, a = 1.6 m in size with B-t = 5 T, and total heating and current drive source power of 80 MW. More ambitious operating modes with higher fusion power reaching the alpha-particle dominated self-heating regime for burning plasma study is possible with the same device hardware, if the more advanced physics is incorporated. Since large vacuum chamber design, possible upgrades both on physics and technologies enable operation of the device with larger plasma configuration and provide potentials to demonstrate key physics issues relevant to DEMO.