@misc{oai:repo.qst.go.jp:00073282,
 author = {逆井, 章 and 鎌田, 裕 and 白井, 浩 and Barabaschi, Pietro and 逆井 章 and 鎌田 裕 and 白井 浩},
 month = {Aug},
 note = {The JT-60SA device, a highly shaped large superconducting tokamak with a variety of plasma control actuators, has been designed in order to contribute to ITER and to complement ITER in all the major areas of fusion plasma development necessary to decide DEMO reactor construction. The procurement and assembly of JT-60SA, shared by EU and Japan, is progressing on track along the project schedule to start operating in 2019. The project has entered the full assembly phase for the Tokamak, Cryoplant, Power Supply, including on-site work at Naka by EU. The EU-JA collaboration for JT-60SA is strong: The Integrated Project Team is able to overcome problems and able to implement the project with efficiency. 
    As of the end of 2015, twenty-seven procurement arrangement (PAs) have been concluded covering 95% of the values of in-kind contribution for JT-60SA. In spite of the large size (~10m order) and weight (few 10 – 100 tonns), components of JT-60SA have been manufactured and assembled well within the tolerance of 1 mm order. EU procures TF coils, most of the power supply systems, cryogenic system, cryostat and so on. The cold test of the first TF coil with a nominal current of 25.7 KA at 4.5-7.0 K was successfully carried out. Japan procures EF coils, Central Solenoids, Vacuum Vessel, thermal shields, heating system, diagnostics system and so on. Vacuum Vessel sectors were welded on the cryostat base forming a 340° torus. The TF coil assembly at Naka will start in Aug. 2016. The heating systems (P-NBI, N-NBI and ECRF) has been conditioned to be operated at their full power (41 MW in total) for 100s. 
    The JT-60SA Research Plan (v.3.3) was documented in Feb. 2016 by 378 co-authors (JA 160 (16 institutes) + EU 213 (14 countries, 30 institutes) + Project Team 5). Detailed assessments and prediction studies of the JT-60SA plasma regimes have confirmed these capabilities: using ITER- and DEMO-relevant plasma regimes, heating conditions, and its sufficiently long discharge duration, JT-60SA enables studies on MHD stability at high beta, heat/particle/momentum transport, high energy ion physics, pedestal physics including ELM control, and divertor physics. By integrating these studies, the project provides ‘simultaneous & steady-state sustainment of the key performance characteristics required for DEMO’ with integrated control scenario development. The JT-60SA experiment is open to the collaborators in the world., The 22nd ANS Topical Meeting on the Technology of Fusion Energy (TOFE 2016)},
 title = {Progress of JT-60SA Construction and Research Planning},
 year = {2016}
}