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Design of the ITER PF Coils.
- Source :
-
IEEE Transactions on Applied Superconductivity . Jun2011, Vol. 21 Issue 3, p1918-1921. 4p. - Publication Year :
- 2011
-
Abstract
- ITER magnets are all designed using superconducting conductors with a high current carrying capability. The Poloidal Field (PF) coils are operated in pulsed mode with maximum operating currents of 48 kA for PF 1 and 6, 55 kA for PF 2,3, and 4 and 52 kA for PF 5. The PF system consists of 6 ring coils, PF1 through PF6, that serve to stabilize the position and control the shape of the plasma in the tokamak. The six PF coils are attached to the outside of the Toroidal Field (TF) coil cases through flexible plates or sliding supports allowing radial displacements. The PF coil positions and sizes have been optimized for the plasma requirements consistent with the constraints imposed by allowing access to the vacuum vessel and by considering pumping ducts to the in-vessel components. [ABSTRACT FROM AUTHOR]
Details
- Language :
- English
- ISSN :
- 10518223
- Volume :
- 21
- Issue :
- 3
- Database :
- Academic Search Index
- Journal :
- IEEE Transactions on Applied Superconductivity
- Publication Type :
- Academic Journal
- Accession number :
- 60968353
- Full Text :
- https://doi.org/10.1109/TASC.2010.2092732