A Poloidal Field Coil System for a High Beta Ignited Tokamak Experiment

A conceptual design of a poloidal field coil system for an ignition and long pulse burn experiment is presented. The coil is located internal to the toroidal field coil and immediately adjacent to the plasma chamber. The advantages this system offers over alternate designs are: sufficient volt-sec to initiate and sustain plasma current for a 300 sec burn, plasma configurations with MHD beta limits in excess of 10%, and the operational flexibility to accommodate a number of different plasma configurations including diverted discharges. For equal ignition margin a divertor configuration requires a larger toroidal field and lower plasma current than a limiter configuration. Power requirements are modest, and technology developments required for construction are within the present state-of-the-art.