ENGINEERING DESIGN OF THE NATIONAL SPHERICAL TOKAMAK EXPERIMENT

The National Spherical Tokamak Experiment (NSTX) is an ultra low aspec t ratio device with a plasma current of 1 MA. The tokamak features aux iliary heating and current drive with a close-fitting conducting shell to maximize the plasma pressure. NSTX is designed for an experimental pulse length that will demonstrate quasisteady state non-inductively driven advanced tokamak operation. The design also takes maximum advan tage of existing facilities and components from previous Princeton dev ices to reduce the overall program costs.