Progress of JT-60SA construction

Ikeda, Yoshitaka; JT-60SA Team

no journal, , 

The main objectives of the JT-60SA are to demonstrate steady-state high-beta plasma, and to support ITER through the optimization of ITER operation scenario. To attain these objectives, the JT-60SA is designed to be the superconducting tokamak with a wide range of diverted plasma configurations. Powerful heating systems of total power of 41 MW for 100s is required to allow the JT-60SA to be operated in break-even equivalent conditions for a long pulse duration. Design and fabrication of JT-60SA components, shared by the EU and Japan, started in 2007. Assembly in the torus hall started in 2013, and welding work of the vacuum vessel sectors is currently ongoing on the cryostat base. Other components such as TF coils, PF coils, power supplies, cryogenic system, cryostat vessel, thermal shields and so on were or are being delivered to the Naka site for installation, assembly and commissioning towards the first plasma in 2019.