Status of the JT-60SA project: An overview on fabrication, assembly and future exploitation

JT-60SA is a superconducting tokamak developed under the Satellite Tokamak Programme of the Broader Approach Agreement between EU and Japan, and the Japanese national programme. It is designed to operate in the break-even conditions for long pulse duration (typically 100 s), with a maximum plasma current of 5.5 MA. Its scientific aim is to contribute at early realization of fusion energy, in support to the ITER project and also to future DEMO devices by addressing key engineering and physical issues for advanced plasma operation. The JT-60SA Project has shown steady progress in the last years: from the design of the main components, started in 2007 in a close collaboration between EU and Japan, continuing through the assembly in the torus hall, started in January 2013 with the delivery of the first large European component, the Cryostat Base. Since then big milestones have been achieved, like the complete winding and pre-installation of the three lower Equilibrium Field (EF) coils, the welding of a 340° of the Vacuum Vessel sectors, and the completion of most of the Toroidal Field (TF) Coils. Outside the tokamak hall, large auxiliary plant like the Cryogenic System (CS) and the Quench Protection Circuits (QPC) have been fully installed and commissioned, while the Switching Network Units (SNU) and TF and EF coils Power Supplies (SCMPS) are completing installation on site. Other components such as Cryostat Vessel, Thermal Shields, In Vessel Components and so forth are being manufactured and being delivered to Naka site for installation and commissioning. This paper gives technical progress on fabrication, installation and assembly of tokamak components and ancillary systems, as well as progress of JT-60SA Research Plan being developed jointly by EU and Japanese fusion communities.