The KSTAR tokamak

Abstract

The KSTAR (Korea Superconducting Tokamak Advanced Research) project is the major effort of the Korean National Fusion Program to design, construct, and operate a steady-state-capable superconducting tokamak. The project is led by Korea Basic Science Institute and shared by national laboratories, universities, and industry along with international collaboration. It is in the conceptual design phase and aims for the first plasma by mid 2002. The key design features of KSTAR are: major radius 1.8 m, minor radius 0.5 m, toroidal field 3.5 T, plasma current 2 MA, and flexible plasma shaping (elongation 2.0; triangularity 0.8; double-null poloidal divertor). Both the toroidal and the poloidal field magnets a r e superconducting coils. The device is configured to be initially capable of 20s pulse operation and then to be upgraded for operation up to 300s with non-inductive current drive. The auxiliary heating and current drive system consists of neutral beam, ICRF, lower hybrid, and ECRF. Deuterium operation is planned with a full radliation shielding.

Numerical study for design of the passive stabilizer and its impact on MHD stability in the proposed KSTAR plasma

“…The proposed Korea Superconducting Tokamak Advanced Research (KSTAR) tokamak [1] will be a versatile facility capable of operating in a wide range of operating modes. The physics goals of the KSTAR program require a machine with considerable flexibility in an operating space in l i and i n : l i (3) from 0.4 to 1.3, and i n of 1.5-5.…”