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Preparation of the manufacture of the ITER correction coils.
- Source :
-
Fusion Engineering & Design . Oct2013, Vol. 88 Issue 9/10, p1478-1481. 4p. - Publication Year :
- 2013
-
Abstract
- Abstract: The ITER correction coils (CC) include three sets of six coils each, distributed symmetrically around the tokamak and inserted between the toroidal field (TF) and the poloidal field (PF) coils. Each pair of coils located on opposite sides with respect to the plasma is series connected with polarity such to produce asymmetric fields. These superconducting coils use a cable-in-conduit conductor, insulated, wound into multiple pancakes and inserted inside an austenitic stainless steel case. The requirements and the main features of the design are presented and the selected options reviewed in terms of their criticality in achieving the specified tolerances. The requested qualification trials are identified and reports the results obtained so far. [Copyright &y& Elsevier]
Details
- Language :
- English
- ISSN :
- 09203796
- Volume :
- 88
- Issue :
- 9/10
- Database :
- Academic Search Index
- Journal :
- Fusion Engineering & Design
- Publication Type :
- Academic Journal
- Accession number :
- 90523885
- Full Text :
- https://doi.org/10.1016/j.fusengdes.2012.12.003