Internal resistive initiation coil electromagnetics in the FED/INTOR baseline design

Some of the electric requirements were determined for radio frequency nonassisted plasma initiation from normal conducting coils inside Tokamak toroidal field coils in the presence of cryostats and other major structures. The effects of bellows or highly insulated sections were also studied. Depending on whether or not insulating sections are used, the field penetration time is 50 to 90 ms, the blip pulse length is 0.15 to 0.19 s, and the power supplied to the blip coils is 400 to 700 MW. Because of its plasma stabilizing effect, a highly conducting vacuum shell is recommended.