Author :
Fairfax, Stephen
Author_Institution :
Plasma Fusion Center, MIT, Cambridge, MA
fDate :
30 Sep-3 Oct 1991
Abstract :
The Alcator C-MOD tokamak at MIT is beginning operation. The device features flexible shaping of noncircular, diverted plasmas, strong ICRF heating, and many innovative engineering features to achieve high performance in a compact device with manned access to the interior of the vacuum vessel. The authors touch upon several of the more innovative aspects of the engineering design. Attention is given to the toroidal field magnet, the vacuum chamber, the poloidal field magnets, the first wall, the power system, the control system, and the radiation shielding
Keywords :
Tokamak devices; fusion reactor safety; fusion reactor theory and design; shielding; Alcator C-MOD tokamak; control system; engineering design; engineering features; first wall; ower system; poloidal field magnets; radiation shielding; strong ICRF heating; toroidal field magnet; vacuum vessel; Design engineering; Heat engines; Magnetic shielding; Plasma devices; Power engineering and energy; Power system control; Power systems; Tokamaks; Toroidal magnetic fields; Vacuum systems;
Conference_Titel :
Fusion Engineering, 1991. Proceedings., 14th IEEE/NPSS Symposium on
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-0132-3
DOI :
10.1109/FUSION.1991.218761
