Nuclear Fusion · 2000 · 202 citations · 2 references
Natural SciencesNuclear EngineeringPhysicsFusion EngineeringNuclear PhysicsPlasma PhysicsFusion PlasmasHigh-temperature PlasmasMagnetic Confinement FusionNuclear FusionPlasma DiagnosticsPlasma HeatingFusion Reactor PhysicsIon Cyclotron WavesNon-inductive Current DrivePlasma Heating SystemsPoloidal Field MagnetsSteady-state Tokamak OperationTokamak PhysicsTokamak Plasmas
KSTAR is Korea’s flagship fusion program, a national effort to advance superconducting tokamak research. The project seeks to build a steady‑state superconducting tokamak that will provide the scientific and technological foundation for a viable fusion reactor. KSTAR features a 1.8‑m major radius, 0.5‑m minor radius tokamak with 3.5‑T toroidal field and 2‑MA plasma current, a 20‑s initial pulse length extendable to 300 s via non‑inductive current drive, and employs neutral beams, ion cyclotron, lower hybrid, and electron cyclotron heating for flexible profile control, supported by a comprehensive diagnostic suite. The project has completed its conceptual design and moved to the engineering design and construction phase, with a target first plasma in 2002.
The Korea Superconducting Tokamak Advanced Research (KSTAR) project is the major effort of the national fusion programme of the Republic of Korea. Its aim is to develop a steady state capable advanced superconducting tokamak to establish a scientific and technological basis for an attractive fusion reactor. The major parameters of the tokamak are: major radius 1.8 m, minor radius 0.5 m, toroidal field 3.5 T and plasma current 2 MA, with a strongly shaped plasma cross-section and double null divertor. The initial pulse length provided by the poloidal magnet system is 20 s, but the pulse length can be increased to 300 s through non-inductive current drive. The plasma heating and current drive system consists of neutral beams, ion cyclotron waves, lower hybrid waves and electron cyclotron waves for flexible profile control in advanced tokamak operating modes. A comprehensive set of diagnostics is planned for plasma control, performance evaluation and physics understanding. The project has completed its conceptual design and moved to the engineering design and construction phase. The target date for the first plasma is 2002.
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Operation at high performance in optimized shear plasmas in JET
A. C. C. Sips, Y. Baranov, C. Challis et al. · Plasma Physics and Controlled Fusion · 1998 · 50 citations
Overview of Korea Superconducting Tokamak Advanced Research diagnostics
S. G. Lee, S. M. Hwang, B. C. Kim et al. · Review of Scientific Instruments · 1999 · 17 citations