Fusion Engineering and Design 88 (2013) 1478–1481 Contents lists available at ScienceDirect Fusion Engineering and Design jo ur n al hom epa ge: www.elsevier.com/locate/fusengdes Preparation of the manufacture of the ITER correction coils P. Libeyre a,∗ , C. Cormany a , N. Dolgetta a , N. Mitchell a , H. Li b , W. Wu c , S. Du c , S. Han c , L. Liu c , Li Wang c , Lin Wang c , J. Wei c , X. Yu c , Z. Zhou c , A. Nijhuis d , S. Sgobba e a ITER Organization, Route de Vinon sur Verdon, 13115 St Paul lez Durance, France b ITER China, 15B Fuxing Road, Beijing 100862, China c ASIPP Shushan Hu Road 350, Hefei, Anhui 230031, China d University of Twente, 7500 AE Enschede, The Netherlands e CERN, CH-1211 Genève 23, Switzerland h i g h l i g h t s ◮ We review the mechanical and electrical requirements on the ITER CC. ◮ He inlets are being developed to keep weld quality while minimizing temperature during welding. ◮ Prototype terminal joints with resistance in the range of 1–2 n have been manufactured. ◮ An insulation mock-up sustained 50 kV for ground insulation without breakdown. ◮ Models of CC cases have been manufactured and welding development is ongoing. a r t i c l e i n f o Article history: Received 11 September 2012 Received in revised form 3 December 2012 Accepted 10 December 2012 Available online 23 January 2013 Keywords: Correction coils Manufacture Winding Impregnation Case a b s t r a c t 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. © 2013 Elsevier B.V. All rights reserved. 1. Introduction The ITER correction coils (CC) include three sets of six coils each, namely the bottom correction coils (BCC), the side correction coils (SCC) and the top correction coils (TCC), distributed symmet- rically around the tokamak and inserted between the toroidal field (TF) and the poloidal field (PF) coils (Fig. 1). They use a super- conducting 10 kA NbTi cable-in-conduit conductor operating up to 5 T, insulated, wound into multiple pancakes and inserted inside an austenitic stainless steel case. The CC are series connected by pair of coils diametrically opposite in the tokamak and electrically connected through dedicated superconducting busbars. The sys- tem results in 9 circuits, each independently powered by a power ∗ Corresponding author. Tel.: +33 4 42 17 69 42. E-mail address: Paul.Libeyre@iter.org (P. Libeyre). converter. The design of this set of coils has been developed by the ITER Organization (IO) [1] and their procurement is now the responsibility of the Chinese Domestic Agency (CNDA), who placed a contract with the Institute of Plasma Physics of the Chinese Academy of Sciences (ASIPP) to manufacture them. The ITER Orga- nization provided CNDA with a built-to-print design including 3D CAD models and 2D drawings. ASIPP is producing the manufactur- ing drawings. The requirements for these coils are derived from the physics requirements and from the various analyses carried out. 2. Requirements 2.1. Coil operation During tokamak operation, the CC have to compensate the low-mode number error fields due to asymmetries in the design, the geometric tolerances during assembly and the influence of 0920-3796/$ – see front matter © 2013 Elsevier B.V. All rights reserved. http://dx.doi.org/10.1016/j.fusengdes.2012.12.003