The plasma confinement of the International Tokamak Experimental Rector (ITER) is provided by the magnetic field generated by 18 toroidal field (TF) coils while 6 poloidal field (PF) and 6 central solenoid coils have the function to drive, shape and pre-heat the plasma. Fusion for Energy (F4E), the European Domestic Agency for ITER, is responsible for the supply of 10 TF coils and 5 PF coils to the ITER project. The ITER Organization (IO) team is instead responsible for the design of such coils as well for the coordination of the activities of the different Domestic Agencies (DAs) producing the different components, and their assembly into the Tokamak. The PF coils utilize NbTi Cable-in-Conduit-Conductor and have different diameters between 8 and 24 meters and weights of up to 400 tons. Regarding the PF coils produced by F4E, so far one has been completed by the Institute of Plasma Physics Chinese Academy of Sciences (ASIPP) under a collaboration agreement with F4E. The other 4 PF coils are being produced at the ITER site in Saint Paul lez Durance, France, under F4E supervision. The first of these (PF5) will be completed by July 2020 while the last coil (PF3) will be ready be the end of 2023. The TF coils utilize Nb3Sn conductor and are manufactured with the “Wind, React & Transfer” method. The first TF coil is close to completion and will be delivered to the ITER site in early 2020. Subsequent TF coils will follow at a rate of about one every 3-4 months. In this article we will report on the production status of both PF and TF coils and, in particular, the different manufacturing strategies employed. The main challenges faced so far and the results obtained are also described.

The magnetic field, necessary for the plasma confinement in the International Thermonuclear Experimental Reactor (ITER), Cadarache, France, is provided by the 18 Toroidal Field Coils (TFC). In each coil, this magnetic field is produced by circulating a current of 68 kA through 4.5 km of Nb3Sn cable-in-conduit superconductor, which is assembled into a mechanical structure capable of withstanding the huge Lorentz forces produced. The Fusion for Energy, the European Domestic Agency for the ITER, is responsible for the supply of 10 TFC. This article gives an overview of the manufacturing and test processes applied during the series production of all sub- and final assemblies, as well as the production status. Special emphasis will be put on some particular characteristics of the Nb3Sn superconductor and other problems faced during manufacturing and strategies applied to overcome them.

The first series components of large D-shaped toroidal field coils (TFC) on the ITER Tokamak project are being fabricated and assembled at European Fusion for Energy (F4E) and Japanese Domestic Agency (JADA) premises since 2013. The TF magnet system consists of 18 individual coils connected in series based on a Nb 3 Sn cable-in-conduit conductors supplied by a 68-kA rated current with an overall 41-GJ stored energy and a peak magnetic field of 11.8 T. One of the key challenges of the construction of the 18 TFCs and their assembly resides in the control of the integration of the large individually manufactured coil components and in the ultimate management of tolerances on the final assembly into the Tokamak pit. This paper presents the integration aspects related to main TFCs subcomponents under fabrication starting from the TF conductor production, the winding of individual double pancakes, and their heat treatment and impregnation. This includes the fabrication of key prototypes for qualification purpose such as helium supply inlets, the electrical joints, and the design of the winding pack insertion into the structural TFC case during the final welding enclosure. Each preassembled 40° sector of a TFCs pair is then integrated into the torus according to tight tolerance requirements to provide both the so-called TF magnetic center line data and to guarantee the final operating wedged design into the inner leg region. The assembly of the coil's terminal is then completed by connecting services through the power feeder busbars, the quench detection high voltage cables and the cryogenics interfaces pipe system.

The ITER Toroidal Field (TF) magnet system consists of 18 "D" shaped coils. Fusion for Energy (F4E), the European Domestic Agency for ITER, is responsible for the supply of 10 out the 19 TF coils (18 installed plus one spare coil). Each TF coil, about 300 t in weight, is made of a stainless steel case containing a Winding Pack (WP).The European manufacturing of the Radial Plates (RPs) and WPs has been awarded to two different industrial partners, whose activities are strongly linked with each other. In order to manufacture a Double Pancake (DP), first, the conductor has to be bent onto a D-shaped double spiral trajectory, then heat treated and inserted in the grooves of the RP. This represents the most challenging manufacturing step: in order to fit inside the groove, the double spiral trajectory of the conductor must match almost perfectly the trajectory of the groove, over a length above 700 m. In order to achieve this, the conductor trajectory length must be controlled with an accuracy of 1 mm over a length of 350 m while the radial plate groove has to be machined with tolerances of +/- 0.2 mm over dimensions of more than 10 m. In order to succeed, it has been essential to develop a metrology process capable to control with high accuracy both the DP conductor and the RP groove trajectories.This paper reports on the work carried out on the development and qualification of the dimensional metrology to monitor the manufacturing of the conductor. Reference is made to the final dimensional check of the RP focusing on the groove centreline length. In addition the results obtained on the one to one scaled prototype DP are described. Finally, the strategy and foreseen improvements for the production of DP's are discussed. (C) 2015 Elsevier B.V. All rights reserved.

In this paper, we will report on the manufacturing of 6 helium inlet mock-ups for the EU ITER TF coils, and on the results of the mock-up tests and other qualification activities carried out in the European industry on this subject.

The superconducting magnet system of ITER consists of four main sub-systems: Toroidal Field (TF) coils, Central Solenoid (CS) coils; Poloidal Field (PF) coils; and Correction Coils (CC). Like many other ITER systems, the magnet components are supplied in-kind by six Domestic Agencies (DAs). The technical specifications, manufacturing processes and procedures required to fabricate these components are particularly challenging. The management structure and organization to realize this procurement within the tight ITER construction schedule is very complex. Fusion for Energy (F4E), the European Domestic Agency for ITER, is in charge of about 25% of the contribution to the ITER magnet system, namely part of the TF and PF conductors, 10 TF coils, 5 PF coils and 9 TF system pre-compression rings. Good progress towards full scale construction has been achieved with the launch of large manufacturing contracts for the production of the superconductor lengths, the fabrication of two full-scale prototypes of the TF coil radial plates, and the start-up of the contract for the construction of 10 TF winding packs. Several tons of advanced Nb3Sn and NbTi strand have been produced, large cabling and jacketing facilities for the conductors and winding lines for the TF coils are being set-up. Tendering actions for the PF coils and pre-compression rings are in progress. Later in 2011 the contracts for the production of the TF radial plates and insertion of the TF coils in the cases will also be launched. This paper reports the progress of the F4E activities as per June 2011.