Engineering features of ISX-B

The ISX-B device will be a major modification of the existing ISX tokamak now in operation at Oak Ridge National Laboratory. This new device will permit the study of intense neutral particle heating and elongated plasmas in the 3 to 5% β range. The modification will consist of replacing the ISX vacuum vessel, torque restraint system and poloidal field coils. The principal design features of the new device are: Major radius of 92 cm, minor radius of 27 cm with a plasma elongation of approximately 1.9 to 1, maximum toroidal field of 1.8 T, maximum vertical field of 0.1 T (with a toroidal field of 1.2 T) and maximum plasma current of 200 kA. A proposal is also available which discusses all aspects of ISX-B. Design of ISX-B began in February 1977, with fabrication of major components starting in June 1977. The present ISX-B schedule calls for completion of all tokamak components and shutdown of the existing ISX in February 1978. The ISX-B device should begin operation in June 1978. The program status at the present seems to support this anticipated start-up