J.H. Schultz, P. Michael, L.M. Myatt (Stone and Webster), and P.W. Wang
Plasma Science & Fusion Center, MIT, Cambridge, MA 02139
W. Reiersen and T. Brown (Northrop-Grumman)
Princeton Plasma Physics Laboratory, P.O. Box 451, Princeton, NJ 08543
K. Kim and S. Baang
Samsung Advanced Institute of Technology, 103-12, Moonji-Dong, Taejon, Korea 305-380
The Korean Superconducting Tokamak Advanced Research project has an all-superconducting magnet system, including 16 toroidal field (TF), 14 poloidal field (PF), and 12 field error correction (FEC) coils. All of the superconducting magnets use cable-in-conduit conductors (CICC) and are cooled by supercritical helium. The TF and PF magnets use an advanced Nb3Sn strand, developed for the International Thermonuclear Experimental Reactor (ITER).
The TF magnets have a peak field of 7.4 T and provide 3.5 T at a major radius of 1.8 m. The TF conductor has 486 strands and can carry a current of 35 kA. The TF system stores 470 MJ and is dumped through a single resistor with a peak terminal-ground voltage of 3 kV.
The PF system can provide 15.8 V-s and inductively drive a highly-shaped 2 MA plasma. All PF coils use 360 strand cable. The outer PF coil pairs are NbTi. The peak field in the PF system during a reference scenario is 7.6 T and the peak current is 23 kA. The peak terminal voltage during plasma initiation is 1.5 kV. The cooling system is adequate to remove 10 kW of nuclear heating and pulsed field losses. The quench detection system is designed to distinguish between quenches and plasma disruptions with a high signal-noise ratio.
* Research supported by Korean Basic Science Institute through Princeton Plasma Physics Laboratory Subcontract S-03966-G