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

Volume

30

Issue

4

fYear

1994

fDate

7/1/1994 12:00:00 AM

Firstpage

1608

Lastpage

1612

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;

fLanguage

English

Journal_Title

Magnetics, IEEE Transactions on

Publisher

ieee

ISSN

0018-9464

Type

jour

DOI

10.1109/20.305568

Filename

305568