Physics of Plasmas · 2008 · 161 citations · 10 references
Natural SciencesNuclear EngineeringPhysicsPlasma PhysicsSurface EngineeringSurface ScienceDivertor EngineeringFusion PlasmasHigh-temperature PlasmasNuclear FusionPlasma ConfinementPlasma Surface TreatmentDivertor MaterialsDivertor PhysicsDivertor Plasma-surface InteractionsEdge Localized Mode MitigationEdge-localized ModesPlasma Facing Components
National Spherical Torus Experiment [which M. Ono et al., Nucl. Fusion 40, 557 (2000)] high-power divertor plasma experiments have shown, for the first time, that benefits from lithium coatings applied to plasma facing components found previously in limited plasmas can occur also in high-power diverted configurations. Lithium coatings were applied with pellets injected into helium discharges, and also with an oven that directed a collimated stream of lithium vapor toward the graphite tiles of the lower center stack and divertor. Lithium oven depositions from a few milligrams to 1g have been applied between discharges. Benefits from the lithium coatings were sometimes, but not always, seen. These benefits sometimes included decreases in plasma density, inductive flux consumption, and edge-localized mode occurrence, and increases in electron temperature, ion temperature, energy confinement, and periods of edge and magnetohydrodynamic quiescence. In addition, reductions in lower divertor D, C, and O luminosity were measured.
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Exploration of spherical torus physics in the NSTX device
M. Ono, S. Kaye, Y.K.M. Peng et al. · Nuclear Fusion · 2000 · 395 citations
Observations concerning the injection of a lithium aerosol into the edge of TFTR discharges
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Recent liquid lithium limiter experiments in CDX-U
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