System studies of Compact Ignition Tokamaks

A new version of the Oak Ridge National Lab. Fusion Engineering Design Center (FEDC) Tokamak System Code (TSC) has been developed to analyze the compact ignition tokamak (CIT). These proposed experiments have small (major radius ≤ 1.5 m) and high-magnetic fields (B ∼ 10T), and are characterized by a lower cost than was estimated for the Tokamak Fusion Core Experiment studies. Key design constraints of CIT include limits to the high stress levels in the magnetic coils, limits to the large temperature rises in the coils and on the first-wall or divertor plate, minimizing power supply requirements, and assuring adequate plasma performance in fusion ignition and burn time consistent with the latest physics understanding. We present systems code level studies of CIT parameter space here for a range of design options with various design constraints