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Active control of the toroidal current density profile is among those plasma control milestones that the National Spherical Tokamak eXperiment - Upgrade (NSTX-U) program must achieve to realize its next-step operational goals, which are characterized by high-performance, long-pulse, MHD-stable plasma operation with neutral beam heating. In this work, a previously developed physics-based control-oriented...
Two key properties that are often used to define a plasma operating scenario in nuclear fusion tokamak devices are the current and electron temperature (Te) profiles due to their intimate relationship to plasma performance and stability. In the tokamak community, the current profile is typically specified in terms of the safety factor (q) profile or its inverse, the rotational transform (ι = 1/q)...
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