The design of a high field ohmic heating coil for a superconducting tokamak based on the US-DPC test coil

Abstract

The fabrication of the US-DPC (demonstration poloidal coil) test coil in the US is using industrial processes capable of manufacturing advanced 30- to 40-kA ternary Nb/sub 3/Sn cable-in-conduit conductors (CICCs) and coils for compact, high-field tokamaks. The authors examine the feasibility of 1- to 1-m-bore 15-T ohmic heating (OH) coils using state-of-the-art CICC conductors. The proof of concept of this technology is expected to be confirmed in the 1990 US-DPC tests at the Japanese Demonstration Poloidal Coil Test Facility. The OH coil design concepts presented appear to satisfy all known superconducting, magnetic, pulsed loss, structural, hydraulic, thermodynamic, and economic requirements of an ohmic heating central solenoid for a compact steady-state tokamak. >