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Preparation of the manufacture of the ITER correction coils.

Authors :
Libeyre, P.
Cormany, C.
Dolgetta, N.
Mitchell, N.
Li, H.
Wu, W.
Du, S.
Han, S.
Liu, L.
Wang, Li
Wang, Lin
Wei, J.
Yu, X.
Zhou, Z.
Nijhuis, A.
Sgobba, S.
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