Title :
Design features of the toroidal field and central solenoid magnet systems
Author :
Kostenko, A. ; Thome, R.J.
Author_Institution :
ITER Joint Central & Home Teams, Ibaraki, Japan
fDate :
7/1/1994 12:00:00 AM
Abstract :
The superconducting coil systems for the International Thermonuclear Test Reactor (ITER) will consist of 24 toroidal field (TF) coils at 488 tonnes each, a central solenoid (CS) at 964 tonnes, and an external poloidal field coil set of 6 coils, the largest of which has a diameter of 30 m. The TF and CS coils will operate at a maximum field at the windings of 13 T and will use Nb3Sn conductor in cable-in-conduit form. The TF coils and the CS are layer wound. The design features of each of these systems are described
Keywords :
Tokamak devices; fusion reactor materials; fusion reactor theory and design; niobium alloys; superconducting cables; superconducting magnets; superconducting materials; tin alloys; 13 T; 30 m; 488 tonne; 964 tonne; ITER; International Thermonuclear Test Reactor; Nb3Sn; Nb3Sn conductor; cable-in-conduit form; central solenoid magnet systems; design features; external poloidal field coil; maximum field; superconducting coil; toroidal field; Conductors; Inductors; Niobium; Solenoids; Superconducting coils; Superconducting magnets; System testing; Tin; Toroidal magnetic fields; Wounds;
Journal_Title :
Magnetics, IEEE Transactions on
