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(FT/P2-09) Advanced Fusion Technologies Developed for JT-60 Superconducting Tokamak

A. Sakasai¹⁾, S. Ishida¹⁾, M. Matsukawa¹⁾, N. Akino¹⁾, T. Ando¹⁾, T. Arai¹⁾, K. Ezato¹⁾, K. Hamada¹⁾, H. Ichige¹⁾, T. Isono¹⁾, A. Kaminaga¹⁾, T. Kato¹⁾, K. Kawano¹⁾, M. Kikuchi¹⁾, K. Kizu¹⁾, N. Koizumi¹⁾, Y. Kudo¹⁾, G. Kurita¹⁾, K. Masaki¹⁾, K. Matsui¹⁾, Y.M. Miura¹⁾, N. Miya¹⁾, Y. Miyo¹⁾, A. Morioka¹⁾, H. Nakajima¹⁾, Y. Nunoya¹⁾, A. Oikawa¹⁾, K. Okuno¹⁾, S. Sakurai¹⁾, T. Sasajima¹⁾, K. Satoh¹⁾, K. Shimizu¹⁾, S. Takeji¹⁾, K. Takenaga¹⁾, H. Tamai¹⁾, M. Taniguchi¹⁾, K. Tobita¹⁾, K. Tsuchiya¹⁾, K. Urata¹⁾, J. Yagyu^1)
 
1) Japan Atomic Energy Research Institute, Naka-machi, Naka-gun, Japan

Abstract.  The modification of JT-60 is planned as a full superconducting tokamak (JT-60SC). The objectives of the JT-60SC program are to establish scientific and technological bases for the steady-state operation of high performance plasmas and utilization of reduced-activation materials in an economically and environmentally attractive DEMO reactor. Advanced fusion technologies relevant to a DEMO reactor have been developed in the superconducting magnet technology and plasma facing components for the design of JT-60SC. To achieve a high current density in a superconducting strand, Nb₃Al strands with a high copper ratio of 4 have been newly developed for the toroidal field coils (TFC) of JT-60SC. The R&D to demonstrate applicability of Nb₃Al conductor to the TFC by a react-and-wind technique have been carried out using a full size Nb₃Al conductor. A full size NbTi conductor with low AC loss using Ni-coated strands has been successfully developed. A forced cooling divertor component with high heat transfer using screw tubes has been developed for the first time. The heat removal performance of the CFC target was successfully demonstrated on the electron beam irradiation stand.

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