Optimization of design point for a fusion energy systems integration test facility FAST

This is the authors' abstract. We don't add key points for this paper.

Fusion by Advanced Superconducting Tokamak (FAST) is a project being proposed as a facility for R&D, testing, and demonstration of systems integration for a deuterium–tritium (DT) fusion energy reactor. The required specifications for FAST are: DT fusion power of 50– 100 MW , neutron wall loading of 0.3– 1 MWm − 2 , discharge duration of 1000 s, and full-power operation lifetime of 1000 h. A quasi-zero-dimensional parameter survey has been carried out to find the parameter region necessary to satisfy the above specifications with the minimum device cost. It was found that a low aspect ratio ( A ∼ 2.3 ), compact (major radius ∼ 2.0 m ) tokamak with high temperature superconductor magnets and neutral beam injection power of about 50 MW (with the energy of 500 keV) offers a possible design point. A time-dependent transport analysis was performed to confirm accessibility to such an operating point and to evaluate the required flux swing for the central solenoid.