作者: L. A. Charlton , D. W. Swain , G. H. Neilson
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摘要: The ISX-B tokamak at ORNL is designed to have 1.8 MW (and eventually 3 MW) of neutral beam power injected heat the plasma. This may raise s? plasna over 5 percent in less than 50 ms, if plasma MHD stable. results a numerical simulation feedback control system and poloidal coil supplies necessary resulting noncircular (D-shaped or elliptical) are presented. shown be straightforward, although nonlinear voltage-current dependence assumed supplies. required supplied coils order contain under high heating rates estimated.