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Normal conducting steady-state toroidal magnet systems are investigated, emphasis being placed on applications to large ignited next generation tokamaks. The study is based on water-cooled tape wound D coils. The data for the TF magnet systems are calculated in a consistent manner with a computer program including the plasma, shield, ohmic heating coil system, and geometric requirements for blanket modules, beam ducts, etc. An optimization procedure is used to find those TF coil systems which minimize cost-relevant quantities. The main results are that normal conducting TF coil systems of ignited next-generation tokamaks (following JET, TFTR, etc.) can be operated in a stationary mode and fed from the grid. Cost for electricity is a relatively small portion of the investment cost even in the case of long integral burn times (>107 s).

Normal conducting steady-state toroidal magnet systems for ignited tokamaks