Plasma Physics and Controlled Fusion · 2012 · 38 citations · 14 references
Natural SciencesNuclear EngineeringPhysicsFusion EngineeringPlasma PhysicsRadiation TransportFusion PlasmasHigh-temperature PlasmasMagnetic Confinement FusionNuclear FusionPlasma ConfinementPlasma-wall InteractionsEnergy Flux ConservationHeat Load DistributionHeating Of Tokamak PlasmasRadiative HeatingTokamak ConfinementTokamak PhysicsTokamak PlasmasToroidal Confinement
FTU plasma discharges with an extremely high amount of Li injection have been performed using a poloidal liquid lithium limiter acting as the principal Li source in the shadow of the main TZN toroidal limiter. Very peculiar of these discharges is the formation of a ‘virtual’ toroidal lithium limiter that redistributes the energy flux to the tokamak vessel first wall by radiative processes and therefore decreases the heat load onto the Mo limiter. These experiments contribute to the investigation of a more complex scenario that will possibly be faced by a project of a liquid lithium divertor in a tokamak with high additional power (or high power load on to the targets).
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Lithium divertor concept and results of supporting experiments
V.A. Evtikhin, I.E. Lyublinski, А.V. Vertkov et al. · Plasma Physics and Controlled Fusion · 2002 · 177 citations
Enhancement of Tokamak Fusion Test Reactor performance by lithium conditioning
D. K. Mansfield, K. W. Hill, J.D. Strachan et al. · Physics of Plasmas · 1996 · 175 citations
Impurity transport in the Pfirsch-Schlüter regime
P. H. Rutherford · The Physics of Fluids · 1974 · 139 citations
First experiments with lithium limiter on FTU
M.L. Apicella, G. Mazzitelli, V. Pericoli Ridolfini et al. · Journal of Nuclear Materials · 2007 · 100 citations