Title :
Design and R&D for the liquid nitrogen cooled poloidal field coil system for the Compact Ignition Tokamak (CIT)
Author :
Thome, R.J. ; Pillsbury, R.D., Jr. ; Bobrov, E.S. ; Williams, J.E.C. ; Vieira, R. ; Feng, J. ; Mann, W.R.
Author_Institution :
Plasma Fusion Center, MIT, Cambridge, MA, USA
fDate :
3/1/1988 12:00:00 AM
Abstract :
The Compact Ignition Tokamak requires a liquid-nitrogen-cooled, pulsed poloidal field coil system for plasma heating, shaping, and control. It will dissipate about 1780 MJ in a total pulse length of 22 s and will require a peak power of 390 MW. The central solenoid will have a bore diameter of 0.68 m, a height of 2.4 m, and a central field of almost 22 T. Geometric restrictions are such that an aggressive structural concept is required; hence, the coil consists of a stack of explosively bonded copper/steel plates. Each plate is cut into eight turns by a water-jet cutting process. Features of the design and selected results from an R&D (research and development) program which is underway are reviewed.
Keywords :
Tokamak devices; coils; 1780 MJ; 2.4 m; 22 s; 390 MW; 68 cm; Compact Ignition Tokamak; R&D program; aggressive structural concept; bore diameter; central field; height; liquid N2 cooling; peak power of 390 MW; plasma heating; pulse length; pulsed poloidal field coil system; stack of explosively bonded copper/steel plates; water-jet cutting process; Coils; Heating; Ignition; Nitrogen; Plasmas; Pulse shaping methods; Research and development; Shape control; Temperature control; Tokamaks;
Journal_Title :
Magnetics, IEEE Transactions on
