Title :
ITER plasma shaping capability: comparison of alternative magnetic configurations
Author_Institution :
Naka Joint Work Site, Ibaraki, Japan
Abstract :
During the last two years four different Poloidal Field configurations have been analyzed in detail and compared. All configurations studied were more or less equivalent from the point of view of plasma performance, two were ruled out for mechanical problems. The PF system, selected as reference, has nine PF coils, all using NbTi superconductors
Keywords :
Tokamak devices; fusion reactor design; niobium alloys; superconducting magnets; titanium alloys; ITER plasma shaping capability; NbTi; NbTi superconductors; alternative magnetic configurations; plasma performance; poloidal field configurations; Conductors; Magnetic analysis; Magnetic flux; Plasma density; Plasma diagnostics; Plasma stability; Plasma waves; Shape control; Superconducting magnets; Toroidal magnetic fields;
Conference_Titel :
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-4226-7
DOI :
10.1109/FUSION.1997.687706
