TFCX-S Toroidal Field Coil Design Using a Superfluid Helium-Cooled Winding

摘要

This paper discusses the design and performance of the toroidal field (TF) coils for one of the possible options for the Tokamak Fusion Core Experiment (TFCX). TFCX is a proposed long-pulse, ignited next-step tokamak to follow the Tokamak Fusion Test Reactor (TFTR). In the TFCX option considered here, designated TFCX-S, there are 16 superconducting TF coils which produce 4.3 T at a plasma major radius of 3.75 m. Each of the TF coils is rated at 5.06 MAT, and operates at a peak field of 9.8 T at the winding. Several winding/cooling approaches have been considered for the TFCX-S TF coils. A NbTi winding, cooled by superfluid helium (He/sub II/) at 1.8 K, is discussed here. The conductor is similar to that being developed by GA Technologies as part of the Department of Energy (DOE) 12 T conductor development program. Use of either sub-cooled atmospheric pressure He/sub II/ or saturated sub-atmospheric pressure He/sub II/ has been considered; both cooling schemes appear feasible. (ERA citation 09:009134)