Mechanical design of a high-beta TFCX tokamak with a demountable TF coil

A TFCX tokamak concept developed by GA Technologies is described. Removal of the poloidal field coils and plasma chamber can be accomplished by simple vertical lifts, after demounting the TF coil upper section. A unique electrical joint allows demounting of the TF coil. Combined-function poloidal field coils located close to the plasma provide versatility in plasma-shaping experiments. Shield modules allow contact maintenance above and below the tokamak, and support the PF coils and plasma chamber. Major penetrations and system interfaces are located at the outboard region for remote maintenance equipment access. (author)