Fig. 2: Control of core and edge instabilities with error field correction (EFC).
From: Tailoring tokamak error fields to control plasma instabilities and transport
a From top to bottom: the time evolution of line averaged density (\({\bar{n}}_{{{{{{{{\rm{e}}}}}}}}}\)) showing a confinement mode transition from the discharge’s initial Low confinement mode (L-mode) to High confinement mode (H-mode), Dα emission (particle recycling light) showing a disruption, ELM crashes and ELM suppression, and 3D coil variables (I = (IT, IM, IB, ϕMT, ϕBM)) with optimized EFC (black), minimized core EF (red), edge resonant EFC (blue), and standard RMP (green). b Distribution of edge-localized and edge-dominant resonant mode on the plasma boundary (\(\delta {B}_{{{{{{{{\rm{n}}}}}}}}}^{{{{{{{{\rm{x}}}}}}}}}\)). c Externally applied normal magnetic field on the plasma boundary (\(\delta {B}_{{{{{{{{\rm{n}}}}}}}}}^{{{{{{{{\rm{x}}}}}}}}}\)) with the KSTAR 3D coils.
