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Ongoing experiments on the National Spherical Torus Experiment have demonstrated ohmic transformer flux savings by initiating the discharge with transient coaxial helicity injection (CHI). The combined use of discharge cleaning of the CHI electrodes and use of lithium evaporation, along with the use of poloidal field coils, to produce a buffer flux that prevents arcs at the top of the device has been...
Coaxial Helicity Injection (CHI), a non-inductive method to initiate plasma and generate toroidal plasma current, is being investigated in the National Spherical Torus Experiment (NSTX). The center stack and outer vacuum vessel are separated by insulating gaps at the top and bottom of the slim central column so that a high voltage (up to 2 kV) can be applied between them from a pulsed power supply...
Summary form only given. Future toroidal magnetic confinement fusion plasma devices such as the Component Test Facility (CTF) require toroidal current drive. Present devices rely on a solenoid to drive current, however, for devices with a high neutron flux, it is impractical to provide the necessary shielding. An alternative method must be provided both to provide toroidal current. A new method of...
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