Title :
Design optimization study of the JT-60 superconducting coil modification
Author_Institution :
Japan Atomic Energy Res. Inst., Ibaraki, Japan
fDate :
6/1/2004 12:00:00 AM
Abstract :
Design optimization of the full superconducting coil tokamak JT-60SC is described. Geometries of both toroidal and poloidal field coils have been changed to allow a lower aspect ratio plasma up to A ∼ 2.8. However, the toroidal magnetic field and flux swing capability are kept as close as possible to the original values to sustain a long flattop period under the break-even class plasma condition using the newly-developed superconducting conductors.
Keywords :
Tokamak devices; fusion reactor design; magnetic flux; optimisation; plasma toroidal confinement; superconducting coils; Cu; JT-60 superconducting coil; Nb3Al; break-even class; design optimization; flux swing capability; plasma condition; poloidal field coils; superconducting conductors; tokamak; toroidal field coils; toroidal magnetic field; Conductors; Copper; Design optimization; Niobium; Plasma devices; Plasma diagnostics; Superconducting coils; Superconducting magnets; Tokamaks; Water heating; $hboxNb_; High Cu ratio; JT-60SC; hboxAl$; react and wind;
Journal_Title :
Applied Superconductivity, IEEE Transactions on
DOI :
10.1109/TASC.2004.830621
