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- W2034287112 abstract "A key goal in the control of a magnetic fusion reactor is to maintain current profiles that are compatible with a high fraction of self-generated non-inductive current as well as with magnetohydrodynamic (MHD) stability at high plasma pressure. This enables high fusion gain and noninductive sustainment of plasma current for steady-state operation. The approach taken toward establishing such plasma current profiles at the DIII-D tokamak is to create the desired profile during the plasma current ramp-up and early flattop phases. The evolution in time of the current profile is related to the evolution of the poloidal flux, which is modeled in normalized cylindrical coordinates using a nonlinear partial differential equation (PDE) usually referred to as the magnetic diffusion equation. We propose, and test in simulations, an extremum-seeking-based, receding-horizon, diffusivity-interior-boundary control scheme designed to match as close as possible a desired current profile within a prespecified time interval." @default.
- W2034287112 created "2016-06-24" @default.
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- W2034287112 date "2008-01-01" @default.
- W2034287112 modified "2023-09-23" @default.
- W2034287112 title "Extremum-Seeking-Based Receding-Horizon Optimal Control of Plasma Current Profile in the DIII-D Tokamak" @default.
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- W2034287112 doi "https://doi.org/10.3182/20080706-5-kr-1001.01697" @default.
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