Engineering design study of JT-60 superconducting modification

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

fYear

2002

fDate

2002

Firstpage

221

Lastpage

225

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;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 2002. 19th Symposium on

Print_ISBN

0-7803-7073-2

Type

conf

DOI

10.1109/FUSION.2002.1027680

Filename

1027680