The KSTAR project: An advanced steady state superconducting tokamak experiment

Abstract

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.

CAD-Based Monte Carlo Neutron Transport KSTAR Analysis for KSTAR

“…Recently authors have augmented a McCARD version with the CAD-based geometry processing module (or McCARD/CAD) by an efficient algorithm for the void space treatment required for the fusion facility analysis. In this paper, we examine the performance of McCARD/CAD for the neutronics analysis of Korea Superconducting Tokamak Advanced Research (KSTAR) device [12].…”

Commissioning of the first KSTAR neutral beam injection system and beam experiments

“…One of the most important issues for the KSTAR tokamak [1] is long pulse operation (300 s) to explore the physics of steadystate fusion plasmas. To achieve the steady state operation of KSTAR in the future, a long pulse (300 s) and high power neutral beam (NB) is mandatory as well as other wave heating systems.…”

Design, fabrication and commissioning of the KSTAR TF current feeder system

“…The 16 TF coils are electrically connected in series and have capacity of feeding steady state currents up to 35.2 kA to generate 3.5 T at the plasma center. Each pair of PF coils has the up-down symmetry and the operating currents are in the range of 20-25 kA [1].…”