July 25, 2023
This project will explore the use of Nb3Sn RRPĀ® superconductors in a compact spherical tokamak (ST) for opportunities for toroidal field (TF) and central solenoid (CS) coils by leveraging the experience, knowledge and modeling capabilities of the Princeton Plasma Physics Laboratory (PPPL). Also, as a head-to-head comparison between low temperature superconductor (LTS) and high temperature superconductor (HTS) technologies this project will evaluate Bi-2212 round conductors. Finally, because the poloidal field (PF) coils are relatively low field (5T-7T), this project will also evaluate the very low cost NbTi conductors (used in MRI machines and manufactured in volumes of hundreds of thousands of kilometers per year). By studying all three conductor types this project expects to recommend an optimum coil system for a compact ST fusion power plant.