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Journal Articles

Status of JT-60SA tokamak under the EU-JA broader approach agreement

Matsukawa, Makoto; Kikuchi, Mitsuru; Fujii, Tsuneyuki; Fujita, Takaaki; Hayashi, Takao; Higashijima, Satoru; Hosogane, Nobuyuki; Ikeda, Yoshitaka; Ide, Shunsuke; Ishida, Shinichi; et al.

Fusion Engineering and Design, 83(7-9), p.795 - 803, 2008/12

 Times Cited Count:17 Percentile:73.62(Nuclear Science & Technology)

no abstracts in English

Journal Articles

JT-60SA toroidal field magnet system

Pizzuto, A.*; Semeraro, L.*; Zani, L.*; Bayetti, P.*; Cucchiaro, A.*; Decool, P.*; della Corte, A.*; Di Zenobio, A.*; Dolgetta, N.*; Duchateau, J. L.*; et al.

IEEE Transactions on Applied Superconductivity, 18(2), p.505 - 508, 2008/06

 Times Cited Count:17 Percentile:64.71(Engineering, Electrical & Electronic)

The Broader Approach agreement between Europe and Japan includes the construction of a fully superconducting tokamak, the JT-60 Super Advanced (JT-60SA), as a satellite experiment to ITER. Toroidal field (TF) magnet which consists of 18 D-shaped coils will be provided to Japan by EU. TF coil main constituents are conductor, winding pack, joints, casing and current leads. The design criteria about conductor and structure were discussed between JA and EU adopted to fulfill the machine requirements. The results of the analyses performed by EU and JA to define and assess the TF magnet system conceptual design, are reported and commented.

Journal Articles

Mechanical design of JT-60SA magnet system

Tsuchiya, Katsuhiko; Suzuki, Yutaka; Kizu, Kaname; Yoshida, Kiyoshi; Tamai, Hiroshi; Matsukawa, Makoto; Dolgetta, N.*; Portafaix, C.*; Zani, L.*; Pizzuto, A.*

IEEE Transactions on Applied Superconductivity, 18(2), p.208 - 211, 2008/06

 Times Cited Count:7 Percentile:42.71(Engineering, Electrical & Electronic)

Magnet system in JT-60SA consists of 18 toroidal field coils, 7 plasma equilibrium field (EF) coils, and central solenoid (CS) that has 4 modules of solenoids. Mechanical design of EF coils and CS is optimized in order to obtain the broad operational space of plasmas that are double-null plasma with high plasma current for high performance operation and ITER-like configuration with IP=3.5MA for ITER-relevant experiment. In the former design, called NCT, divertor coil (EF4) is made of Nb$$_{3}$$Sn conductor, as well as CS conductor. However, it is clear that 6.2T of Bmax is significant to operate ITER-like plasma. Therefore, material of cable for EF4 conductor is changed into NbTi, so that this contributes to cost reduction. Regarding CS design, material of conduit is changed into JK2LB in order to simplify the structure of pre-compression. Stress analysis for support structure and winding pack of EF coils and CS is currently carried out. In the case where the vertical unbalance force of CS is largest in the designed plasma operation, peak stress of conduit is less than fatigue limit in 18,000 cycles that is designed number of plasma shot in JT-60SA. This result shows the recent design of CS conductor has significant mechanical strength.

Journal Articles

A New design for JT-60SA Toroidal field coils conductor and joints

Zani, L.*; Pizzuto, A.*; Semeraro, L.*; Ciazynski, D.*; Cucchiaro, A.*; Decool, P.*; della Corte, A.*; Di Zenobio, A.*; Dolgetta, N.*; Duchateau, J. L.*; et al.

IEEE Transactions on Applied Superconductivity, 18(2), p.216 - 219, 2008/06

 Times Cited Count:4 Percentile:31.1(Engineering, Electrical & Electronic)

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.

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