The compact ignition tokamak (CIT)

Summary form only given. The compact ignition tokamak (CIT) experiment is designed to establish the scientific feasibility of power production from the fusion process and to establish the basis of alpha particle physics for follow-on steps toward a magnetic confinement fusion reactor. The present design incorporates all those features which have been shown to improve tokamak performance. Since both the tokamak energy confinement and beta limit have been shown to be proportional to plasma current. CIT will operate at a high plasma current, I _P= 12.3 MA. A vertically elongated (k=2.0) double-null divertor plasma cross section was chosen to allow high I_P per unit toroidal field and to allow access to optimal tokamak confinement regimes. The high toroidal magnetic field B_T =11T and compact size (R=2.14 m, a=0.66 m) are chosen within the constraints of allowable stress limits to support the high plasma current and reach ignition in a modest size and cost device. As its research program unfolds, CIT will progressively work through the physics issues of burning, alpha-heated plasmas to provide the information necessary for future devices