Conveners
Divertor & SOL Physics 1: EX/2 & TH/2
- Ulrich Stroth (Max-Planck-Institut für Plasmaphysik)
Dr
Adam McLean
(Lawrence Livermore National Laboratory)
19/10/2016, 10:45
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Oral
A comprehensive experimental campaign at DIII-D has advanced understanding and modeling of the effects of drifts and radiating species in diverted plasma up to ITER-relevant collisionality. Unique diagnostic capabilities are employed to show directly that plasma drifts lead to in/out asymmetries as well as shifts in radial parameter profiles throughout the divertor legs, and are a critical...
Dr
Daniel Carralero
(IPP Garching)
19/10/2016, 11:05
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Oral
Heat and particle transport onto plasma-facing components is a key issue for next generation tokamaks, as it will determine the erosion levels and the heat loads at the main chamber first wall. In the Scrape-off Layer (SOL), this transport is thought to be dominated by the perpendicular convection of filaments. In this work, we present recent experiments which have led to an improved picture...
Dr
Choong-Seock Chang
(Princeton Plasma Physics Laboratory)
19/10/2016, 11:25
THD - Magnetic Confinement Theory and Modelling: Plasma–material interactions; divertors, limiters, SOL
Oral
The edge gyrokinetic code XGC1 shows that the divertor heat flux width λq in between ELMs of Type I ELMy H-modes in two representative types of present tokamaks (DIII-D type for conventional aspect ratio and NSTX type for tight aspect ratio) is set mostly by the ion neoclassical orbit spread, which is proportional to 1/Ip, while the blobby turbulent spread plays a minor role. This explains...
Dr
Holger Reimerdes
(Ecole Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC))
19/10/2016, 11:45
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Oral
Present research towards a plasma exhaust solution for a fusion power plant aims at validating edge physics models to strengthen the predictive capabilities and improving the operating regime and the divertor configuration. The TCV tokamak is used in particular to investigate to what extent geometric modifications of the configuration can affect the plasma exhaust performance by decreasing the...
Dr
Ilya Senichenkov
(Saint Petersburg State Polytechnical University)
19/10/2016, 12:05
THD - Magnetic Confinement Theory and Modelling: Plasma–material interactions; divertors, limiters, SOL
Oral
Our current understanding of divertor physics indicates that at least partial detachment will be a necessary condition for operation of future fusion power devices such as ITER, DEMO and beyond. In recent years a divertor operation with complete detachment was achieved in full tungsten ASDEX Upgrade with nitrogen seeding [Potzel et al Nucl. Fusion 54 (2014) 013001, Reimold et al Nucl. Fusion...
