Development of the ITER PF Coils

Author

Lim, B.S. ; Simon, F. ; Ilin, Y. ; Gung, C.Y. ; Boyer, C. ; Beemsterboer, C. ; Valente, P. ; Lelekhov, S. ; Mitchell, N.

Author_Institution

Tokamak Dept., ITER Int. Organ., St. Paul-lez-Durance, France

Volume

22

Issue

3

fYear

2012

fDate

6/1/2012 12:00:00 AM

Firstpage

4201404

Lastpage

4201404

Abstract

The ITER Poloidal Field (PF) magnet system consists of six coils. Niobium-Titanium (NbTi) is used as superconducting material and cable-in-conduit conductor(CICC) type are used as a conductor. All coils are fabricated by stacking 6 to 9 double-pancakes wound by two-in-hand winding scheme. The six PF coils (PF1 to PF6) are attached to the Toroidal Field (TF) coil cases through flexible plates or sliding supports to allow small radial and vertical displacements. The outer diameters of the coils vary between 8 m and 24 m. Since the PF coil system provides magnetic field for plasma shaping and position control together with the Central Solenoid (CS) coil, it needs to operate in fast pulse mode, leading to induced voltages of up to 14 kV on the coil terminals during operation.

Keywords

superconducting coils; superconducting materials; ITER PF coils; ITER poloidal field magnet system; NbTi; PF coil system; cable-in-conduit conductor; central solenoid coil; flexible plates; niobium-titanium; plasma shaping; position control; sliding supports; superconducting material; toroidal field coil; two-in-hand winding scheme; Coils; Conductors; Insulation; Joints; Manufacturing; Plasmas; Windings; Fusion; ITER; PF coil; superconductor;

fLanguage

English

Journal_Title

Applied Superconductivity, IEEE Transactions on

Publisher

ieee

ISSN

1051-8223

Type

jour

DOI

10.1109/TASC.2011.2174564

Filename

6069557