Structural analysis of the International Thermonuclear Experimental Reactor magnet system: comparative study of two central solenoid configurations
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The International Thermonuclear Experimental Reactor (ITER) tokamak superconducting magnet system is designed to confine and control a 21 MA plasma during the various phases of pulsed operation. The central solenoid (CS) and poloidal coils are independently powered with currents that cycle during the pulse. The reference magnet system design includes a layer-wound 12 meter long CS that only allows one current density distribution. In an alternative design, which shows advantages for plasma shape control, the CS consists of three independently powered modules. In this paper the configurations are compared from the structural point of view.
[1] P. L. Mondino. ITER plasma shaping capability: comparison of alternative magnetic configurations , 1997, 17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131).
[2] Anatoly Panin,et al. Finite element analysis of effective mechanical and thermal characteristics of microheterogeneous superconducting toroidal field coils , 1992 .