Full Paper
IAEA-CN77
Contents  Return  Previous Page  Next Page  Index


Return To: Session OV7/FT - Fusion Technology
Prev Page: Session OV7/FT - Fusion Technology
Next Page: (FT/4) The Helias Reactor


(OV7/1) Design and Construction of the KSTAR Tokamak

G. S. Lee1) and the KSTAR Team
 
1) Korea Basic Science Institute, Korea

Abstract.  The extensive design effort 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 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, vacuum vessel, plasma facing components, and power supplies. The new KSTAR experimental facility with cryogenic system and de-ionized water-cooling and main power systems has been designed, and the construction work has been on-going for completion in year 2004.

Read the full paper in PDF format.

IAEA 2001