CIT physics and engineering basis

The CIT is a high-field, compact tokamak design whose objective is the study of physics issues associated with burning plasmas. The toroidal and poloidal field coils employ a copper-steel laminate, manufactured by explosive-bonding techniques, to support the forces generated by the design fields: 10 T toroidal field at the plasma center, and 21 T in the OH solenoid. A combination of internal and external PF coils provide control of the equilibrium and the ability to sweep the magnetic separatrix across the divertor plates during a pulse. At temperatures and {beta}{sub {alpha}} levels characteristic of ITER designs, the fusion power in CIT approaches 800 MW and can be the limiting factor in the pulse length. Ignition requires that the confinement time exceed present L-mode scalings by about a factor-of-two, which is anticipated to occur as a result of the operational flexibility incorporated into the design. Conventional operating limits given by {r angle}{beta}{l angle} < 3I/aB, {bar n}{sub 20} < 2B/Rq{sub e} and q{sub {Psi}} {le} 3.2 have been chosen and, in the case of MHD limits, have been justified by ideal stability analysis. The power required for CIT ignition ranges from 10 MW to 40 MW or more, depending on confinementmore » assumptions, and either ICRF or ECRF heating, or both, will be used. 12 refs., 6 figs.« less