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