The JT-60SA is an advanced tokamak device under construction, which addresses key physics issues for ITER and DEMO. The emphasis of JT-60SA's research aims is to extend the reactor-relevant plasma pulse length towards steady state, thus the superconducting magnet is introduced for the plasma confinement. The construction of the magnet system is in progress under the collaboration between Japan and Europe. For example, manufacturing/installation of the toroidal field coils is split primarily between sites in Italy (conductor cabling and jacketing, casings fabrication, coil winding and integration), France (support structures, coil winding and integration and eventual cold testing) and Japan (on-site installation). This paper overviews the progress in the manufacturing of the JT-60SA magnet system, highlighting the engineering solutions that have been adopted.
Progress in the superconducting magnet systemThe superconducting magnet system consists of 18 toroidal field (TF) coils, a central solenoid (CS) with 4 modules, 6 equilibrium field (EF) coils (figure 1), as well as high temperature superconductor current leads (HTS CLs), and electrical