A compact ignition experiment

A national design team, with representation from essentially all of the major US fusion laboratories, has developed the conceptual design for a compact tokamak device to build on the good results from existing tokamak experiments. This device is called the Compact Ignition Tokamak (CIT), and has the mission of 'realizing, studying, and optimizing ignited plasma operation'. The features of this are compact size, liquid nitrogen precooled copper coils producing about 10 T toroidal field and about 10 MA plasma current at plasma elongations of two, divertor and limiter operation, and ICRF heating. (author). 7 refs, 2 figs