The extensive design effort for KSTAR has been focused on two major aspects of the KSTAR
project mission - steady-state-operation capability and advanced tokamak physics. The steady
state aspect of the mission is reflected in the choice of superconducting magnets, provision of
actively cooled in-vessel components, and long pulse current drive and heating systems. The
advanced tokamak aspect of the mission is incorporated in the design features associated with
flexible plasma shaping, double null divertor and passive stabilizers, internal control coils and
a comprehensive set of diagnostics. Substantial progress in engineering has been made on
superconducting magnets, the vacuum vessel, plasma facing components and power supplies. The
new KSTAR experimental facility with cryogenic system and deionized water cooling and main
power systems has been designed, and the construction work is under way for completion
in 2004.
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.
A plasma generator for a long pulse H(+)/D(+) ion source has been developed. The plasma generator was designed to produce 65 A H(+)/D(+) beams at an energy of 120 keV from an ion extraction area of 12 cm in width and 45 cm in length. Configuration of the plasma generator is a multi-cusp bucket type with SmCo permanent magnets. Dimension of a plasma chamber is 25 cm in width, 59 cm in length, and 32.5 cm in depth. The plasma generator was designed and fabricated at Japan Atomic Energy Agency. Source plasma generation and beam extraction tests for hydrogen coupling with an accelerator of the KSTAR ion source have been performed at the KSTAR neutral beam test stand under the agreement of Japan-Korea collaborative experiment. Spatial uniformity of the source plasma at the extraction region was measured using Langmuir probes and ±7% of the deviation from an averaged ion saturation current density was obtained. A long pulse test of the plasma generation up to 200 s with an arc discharge power of 70 kW has been successfully demonstrated. The arc discharge power satisfies the requirement of the beam production for the KSTAR NBI. A 70 keV, 41 A, 5 s hydrogen ion beam has been extracted with a high arc efficiency of 0.9 -1.1 A/kW at a beam extraction experiment. A deuteron yield of 77% was measured even at a low beam current density of 73 mA/cm(2).
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