Abstract:Abstract.A major challenge for spherical tokamak development is to start-up and ramp-up the plasma current (I p ) without using a central solenoid. Experiments in the National Spherical Torus eXperiment (NSTX) demonstrated that 1.4 MW of 30 MHz high-harmonic fast wave (HHFW) power could generate an I p = 300 kA H-mode discharge with a non-inductive I p fraction, f NI ~ 0.7. The discharge had an axial toroidal magnetic field (B T (0)) of 0.55 T, the maximum B T (0) available on NSTX. NSTX has undergone a major … Show more
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