Numerical study for determining PF coil system parameters in MHD equilibrium of KT-2 tokamak plasma

Summary form only given. The KT-2 is a large-aspect-ratio medium-sized divertor tokamak being in the conceptual design phase and planned to be operational in 1998 at the Korea Atomic Energy Research Institute (KAERI), which has major radius 1.4 m, minor radius 0.25 m, toroidal magnetic field 3T and fast wave current drive (FWCD) as a main drive for seed current at the plasma center. Plasma equilibrium in tokamak can be acquired by controlling the current of poloidal field (PF) coils in appropriate geometries and positions. In this study, we have performed numerical calculations to achieve the various equilibrium conditions fitting given plasma shapes and satisfying PF current limitations. Usually an ideal magnetohydrodynamic (MHD) equation is used to obtain the equilibrium solution of tokamak plasma, and it is practical to take advantage of a numerical method in solving the MHD equation because it has nonlinear source terms. Two equilibrium codes have been applied to find a double-null configuration of free-boundary tokamak plasma in KT-2: one is of our own developing and the other is a free-boundary tokamak equilibrium code (FBT) that has been used mainly for the verification of developed code´s results.