Assessment of the radial plate design of the ITER TF coil winding pack

The Reduced Technical Objectives/Reduced Cost (RTO/RC) ITER Toroidal Field coil system is being designed to provide the magnetic field necessary to maintain a 13.3 MA plasma in a tokamak configuration. During operation the toroidal field coils experience an electromagnetic load toward the machine axis. This load is resisted by wedging the inboard legs of the TF coil cases. Two design options are considered for the winding pack of the ITER toroidal field coils. In this paper a comparison between the two design options is made in terms of design features, manufacturing issues, cost estimate and stresses in the insulation, conductor jacket and steel structure.