Magnet scenario design and analysis for ITER

Author

Schultz, J.H. ; Wesley, J. ; Bulmer, R. ; Kerns, J. ; Shen, S. ; Miller, J.

Author_Institution

Plasma Fusion Center, MIT, Cambridge, MA, USA

fYear

1989

fDate

2-6 Oct 1989

Firstpage

36

Abstract

ITER (International Thermonuclear Experimental Reactor) is a collaborative design by the United States, Europe, Japan and the Soviet Union for a tokamak fusion reactor that would demonstrate the physics and test the technology needed for commercial fusion reactors. The poloidal field (PF) magnets are responsible for forming and shaping highly elongated, high-current plasmas during a long-pulse burn. The toroidal field (TF) system consists of 16 magnets with single-grade, rectangular winding packs. The conductor is an internally-cooled, ternary Nb₃Sn. This conductor is also used in the high-field PF coils. All PF coils external to the TF system are superconducting, using internally-cooled, cable-in-conduit conductor

Keywords

Tokamak devices; fusion reactor materials; fusion reactor theory and design; superconducting magnets; ITER; International Thermonuclear Experimental Reactor; Nb₃Sn; cable-in-conduit conductor; tokamak fusion reactor; winding packs; Conductors; Fusion reactor design; Fusion reactors; Inductors; International collaboration; Magnetic analysis; Superconducting cables; Superconducting coils; Superconducting magnets; Toroidal magnetic fields;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on

Conference_Location

Knoxville, TN

Type

conf

DOI

10.1109/FUSION.1989.102166

Filename

102166