Approaching ITER PF Coil Manufacturing

Abstract

The ITER poloidal field (PF) coil system provides a magnetic field for plasma shaping and position control together with the central solenoid coils; it needs to operate in a fast pulse mode, leading to induced voltages of up to 14 kV on the coil terminals during operation. The PF magnet system consists of six coils. The cable-in-conduit conductors with niobium-titanium (NbTi) superconducting material are used in the coils. All coils are fabricated by stacking six to nine double pancakes wound by two-in-hand winding scheme. The six PF coils (PF1 to PF6) are attached to the toroidal field coil cases through the flexible plates or sliding supports to allow small radial and vertical displacements. The PF coils will be procured by the European and Russian domestic agencies under separate procurement arrangements. To accelerate the PF6 coil schedule, which is one of the critical paths for the ITER schedule, a cooperation agreement has been placed between F4E and ASIPP in China in October 2013 with the CN-DA support. Before starting the manufacturing of the coil, the component qualification has been started, such as the 3 × 3 conductor mock-up, turn insulation, and helium inlet with the dummy conductors. Corresponding mechanical and electric tests were carried out at room temperature and 77 K. The PF dummy double pancake is also wound to demonstrate the winding. This paper presents the updated design for manufacturing of components. Their fabrication methods are also described. This paper concludes with a summary state report on PF1 dummy winding.