Back to Search Start Over

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

Authors :
Gauthier, F.
Foussat, A.
Shuangsong, D.
Bessette, D.
Jong, C. T. J.
Libeyre, P.
Mitchell, N.
Source :
IEEE Transactions on Applied Superconductivity. Jun2012, Vol. 22 Issue 3, p4902404-4902404. 4p.
Publication Year :
2012

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. [ABSTRACT FROM PUBLISHER]

Details

Language :
English
ISSN :
10518223
Volume :
22
Issue :
3
Database :
Academic Search Index
Journal :
IEEE Transactions on Applied Superconductivity
Publication Type :
Academic Journal
Accession number :
76519471
Full Text :
https://doi.org/10.1109/TASC.2011.2174581