학술논문

Engineering design study of JT-60 superconducting modification
Document Type
Conference
Source
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231) Fusion engineering Fusion Engineering, 2002. 19th Symposium on. :221-225 2002
Subject
Fields, Waves and Electromagnetics
Nuclear Engineering
Design engineering
Superconducting coils
Inductors
Plasma materials processing
Steel
Superconducting magnets
Tokamaks
Power generation economics
Environmental economics
Steady-state
Language
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.