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A New Design for JT-60SA Toroidal Field Coils Conductor and Joints

By: Zani, L.; Yoshida, K.; Villari, R.; Verger, J.-M.; Turtu, S.; Turck, B.; Roccella, S.; Ramogida, G.; Portafaix, C.; Petrizzi, L.; Nicollet, S.; Muzzi, L.; Molinie, F.; Lacroix, B.; Kikuchi, M.; Hertout, P.; Duchateau, J.-L.; Dolgetta, N.; Di Zenobio, A.; della Corte, A.; Decool, P.; Cucchiaro, A.; Ciazynski, D.; Semeraro, L.; Pizzuto, A.;

2008 / IEEE


This item was taken from the IEEE Periodical ' A New Design for JT-60SA Toroidal Field Coils Conductor and Joints ' The upgrade of JT-60U to JT-60 Super Advanced (JT-60SA), a fully superconducting tokamak, will be performed in the framework of the Broader Approach (BA) agreement between Europe (EU) and Japan. In particular, the Toroidal Field (TF) system, which includes 18 coils, is foreseen to be procured by France, Italy and Germany. This work covers activities from design and manufacturing to shipping to Japan. The present paper is mainly devoted to the analyses that lead to the conductor design and to the technical specifications of the joints for the JT-60SA TF coils. The conductor geometry is described, which is derived from Cable-In-Conduit concept and adapted to the actual JT-60SA tokamak operating conditions, principally the ITER-like scenario. The reported simulations and calculations are particularly dealing with the stability analysis and the power deposition during normal and off-normal conditions (AC losses, nuclear heating). The final conductor solution was selected through a trade-off between scientific approach and industrial technical orientation. Besides, the TF system connections layout is shown, derived from the industrially assessed twin-box concept, together with the associated thermo-hydraulic calculations ensuring a proper temperature margin.