Nuclear Fusion · 1983 · 97 citations · 9 references
Natural SciencesPhysicsFusion EngineeringHeat TransferPlasma PhysicsDivertor EngineeringNeutral Beam InjectionPlasma DiagnosticsPlasma HeatingPlasma SimulationPlasma TransportBulk DensityDivertor ModelingDivertor PhysicsDivertor SimulationElectric Field LinesPuffingPuffing Phenomena
Scrape-off plasma parameters have been measured in ASDEX both in the divertor chamber and in the mid-plane, for neutral-injection powers of up to 2.5 MW. Measurements demonstrate the existence of strong inhomogeneities parallel to the field lines and show the dependence of divertor density and temperature on bulk plasma density, heating power and mode of divertor operation (gettered/ungettered, different divertor slit widths, additional gas puffing in the divertor). Three recycling regimes, characterized by different dependences of the divertor density on the bulk plasma density, are identified in agreement with a numerical fluid model of the scrape-off plasma. In the particularly attractive high-recycling regime, divertor temperatures could be kept around 7 eV for the whole range of heating powers tested.
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Plasma–wall transition in an oblique magnetic field
R. Chodura · The Physics of Fluids · 1982 · 513 citations · Full text
Cool, High-Density Regime for Poloidal Divertors
M. Petravić, D.E. Post, D. Heifetz et al. · Physical Review Letters · 1982 · 113 citations
Plasma Boundary Layer in Limiter and Divertor Tokamaks
M. Keilhacker, K. Lackner, K. Behringer et al. · Physica Scripta · 1982 · 79 citations
Helium Ash Exhaust with Single-Null Poloidal Divertor in Doublet III
M. Shimada, M. Nagami, K. Ioki et al. · Physical Review Letters · 1981 · 73 citations