Quasi 3D Thermo-Hydraulic Modeling and Conductor Temperatures of the ITER Correction Coils

Author

Gauthier, Francois ; Foussat, A. ; Shuangsong, D. ; Bessette, D. ; Jong, C.T.J. ; Libeyre, P. ; Mitchell, N.

Author_Institution

Soditech Ing., Cannes La Bocca, France

Volume

22

Issue

3

fYear

2012

fDate

6/1/2012 12:00:00 AM

Firstpage

4902404

Lastpage

4902404

Abstract

The ITER magnet system consists of 4 sub-systems: 3 sets of 6 Correction Coils (CC), a Central Solenoid (CS), 6 Poloidal Field coils (PF) and 18 Toroidal Field Coils (TFC). The Correction Coil system aims to correct particular asymmetries and reduce error magnetic fields responsible for locked modes which can induce plasma disruptions. During the plasma scenario, thermal shield radiation, eddy current losses in structures, conduction from the TFC casing and AC losses in the NbTi superconductor will decrease the temperature margin of the CC conductor.

Keywords

eddy current losses; finite element analysis; heat radiation; magnetic fields; superconducting coils; superconducting magnets; 18 toroidal field coils; AC losses; ANSYS code; BCC; CC conductor; CS; GANDALF; ITER correction coils; ITER magnet system; PF; SCC; TFC; bottom correction coils; central solenoid; conductor temperatures; eddy current losses; error magnetic field reduction; plasma scenario; quasi-3D finite element thermo-hydraulic analyses; side correction coils; superconductor; thermal shield radiation; Coils; Conductors; Heating; Helium; Plasma temperature; Solid modeling; Three dimensional displays; Cable in conduit conductor; ITER; correction coils; thermo-hydraulics;

fLanguage

English

Journal_Title

Applied Superconductivity, IEEE Transactions on

Publisher

ieee

ISSN

1051-8223

Type

jour

DOI

10.1109/TASC.2011.2174581

Filename

6082393