Author :
Sakasai, A. ; Ishida, S. ; Matsukawa, M. ; Kurita, G. ; Akino, N. ; Ando, T. ; Arai, T. ; Ichige, H. ; Kaminaga, A. ; Kato, T. ; Kizu, K. ; Masaki, K. ; Miura, Y.M. ; Miyo, Y. ; Morioka, A. ; Sakurai, S. ; Sasajima, T. ; Takeji, S. ; Tamai, H. ; Tsuchiya,
Author_Institution :
Naka Fusion Res. Establ., JAERI, Ibaraki, Japan
Abstract :
The modification of JT-60 is planned as a fully superconducting tokamak (JT-60SC). The mission of JT-60SC program is to establish scientific and technological bases for an advanced operation in an economically and environmentally attractive DEMO reactor and ITER. The research objectives are to accomplish high performance steady state operation with high beta and non-inductive full current drive, with high bootstrap current fraction, and demonstrate the plasma applicability of reduced-activation material for a plasma of break-even class relevant to the reactor plasma. Basic design of JT-60SC has been completed and the detailed design is under way. The engineering design for main components of JT-60SC is described.
Keywords :
Tokamak devices; fusion reactor design; plasma toroidal confinement; superconducting magnets; DEMO; JT-60; JT-60SC; bootstrap current fraction; break-even; superconducting magnets; superconducting tokamak; Design engineering; Environmental economics; Inductors; Plasma materials processing; Power generation economics; Steady-state; Steel; Superconducting coils; Superconducting magnets; Tokamaks;
