The design of the Korea Superconducting Tokamak Advanced Research(KSTAR)

摘要

The KSTAR team is carrying out the design and research anddevelopment for a steady-state-capable advanced superconducting tokamakto establish the basis for an attractive fusion reactor as a futureenergy source. The physics requirements are driven by the plasma controland exhaust capabilities needed to extend the performance and pulselength of tokamak plasmas. The tokamak has major radius 1.8 m, minorradius 0.5 m, toroidal field 3.5 T and plasma current 2 MA, a stronglyshaped plasma cross-section shaping (elongation 2.0 and triangularity0.8), and a double-null poloidal divertor. The initial pulse length is20 s, long enough to study physics on confinement timescales, but shortenough to permit economical plasma-facing component technology. Thepulse length can be increased to 300 s through upgrades. The machinewill be operable in either hydrogen or deuterium, but neutron yieldswill be constrained to avoid the cost and inconvenience of remotemaintenance and low-activation materials. The magnet system provides aninductively driven 20 s pulse with full current, beta, and shaping. Withnon-inductive current drive, steady-state plasmas can be sustained overa wide range of profile shapes and plasma pressures, Passive structuresare provided to stabilize the vertical instability and high-beta modesand internal coils are provided for fast position control. The divertorstructures are designed for particle removal, recycling control,impurity control, and flexibility for advanced divertor operation. Theplasma heating system is designed for heating, current-drive, profilecontrol, and flexibility. It will deliver power via neutral beams (8MW), ion-cyclotron waves (6 MW), and lower-hybrid waves (1.5 MW), eachof which can be expanded through upgrades. A comprehensive set ofdiagnostics is planned for plasma control, performance evaluation, andphysics understanding