Engineering design study of JT-60 superconducting modification
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231) - Trang 221-225
Tóm tắt
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.
Từ khóa
#Design engineering #Superconducting coils #Inductors #Plasma materials processing #Steel #Superconducting magnets #Tokamaks #Power generation economics #Environmental economics #Steady-stateTài liệu tham khảo
ishida, 0, This Symposium
seki, 1990, Proc 13th IAEA Conf on Controlled Nuclear Fusion and Plasma Physics
ando, 2001, Proceedings of the 15thInt Conf on Magnet Technology
sato, 2001, Proc In 7thIAEA TCM on Energetic Particles in Magnetic Confinement Systems, 8
miura, 0, Proe 17th Int Conf on Magnet Technology Jeneve 2001 to be published in IEEE Tran Appl Supercond
kizu, 2001, Proceedings of the 15thInt Conf on Magnet Technology
okano, 1998, Fusion Eng Des, 41, 10.1016/S0920-3796(97)00193-2
sakurai, 2001, Proc IAEA TCM on Divertor Concepts
kikuchi, 1990, Nucl Fusion, 30