A simple analytic fluid model based on particle and momentum conservation describes the response of the scrape-off layer to an applied radial electric field. The model explains why the variation of plenum pressure during limiter biasing in TEXTOR shows the opposite behaviour as divertor biasing in Tokamak de Varennes: the mechanical baffles that define the throats of the pump limiter are aligned along the magnetic field, thus preventing collection of the induced perpendicular flux when the drift is directed towards the scoop. Rather, the optimal pumping is expected when the drift is directed away from the scoop due to the increase of the parallel flux needed to satisfy the Bohm-Chodura criterion. Qualitative agreement is obtained with measu...
Large neutral gas accumulation has been observed in trapped volumes directly behind the mechanical l...
International audienceMotivated by Radio Frequency (RF) heating studies, the response of the plasma ...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, Fe...
The two-dimensional multifluid code TECXY has been used to model the biasing (with respect to the fi...
The 2D multifluid code TECXY has been used to model the experimental biasing of the toroidal belt li...
The design of a pump limiter depends strongly on the details of the plasma scrapeoff zone. A model h...
Pump limiters are mechanical devices for He-ash removal, fuel particle control, and possibly impurit...
In the Tore Supra tokamak, the scrape-off layer profiles of discharges limited either on the inboard...
The current flowing between the new toroidal pump limiter of Tore Supra and the inner wall component...
The heat load on plasma-facing components is a key issue for forthcoming fusion experiments. In this...
The reversed field pinch (RFP) plasma performance, as in the Tokamak, is strongly correlated with th...
The Advanced Limiter Test (ALT) project is the focus of a fruitful and intense International Energy ...
The heat load on plasma-facing components is a key issue for forthcoming fusion experiments. In this...
The existing 2-d two-fluid code for computing the plasma profiles in the scrape-off layer of limiter...
A heuristic model for the plasma scrape-off width balances magnetic drifts against parallel loss at ...
Large neutral gas accumulation has been observed in trapped volumes directly behind the mechanical l...
International audienceMotivated by Radio Frequency (RF) heating studies, the response of the plasma ...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, Fe...
The two-dimensional multifluid code TECXY has been used to model the biasing (with respect to the fi...
The 2D multifluid code TECXY has been used to model the experimental biasing of the toroidal belt li...
The design of a pump limiter depends strongly on the details of the plasma scrapeoff zone. A model h...
Pump limiters are mechanical devices for He-ash removal, fuel particle control, and possibly impurit...
In the Tore Supra tokamak, the scrape-off layer profiles of discharges limited either on the inboard...
The current flowing between the new toroidal pump limiter of Tore Supra and the inner wall component...
The heat load on plasma-facing components is a key issue for forthcoming fusion experiments. In this...
The reversed field pinch (RFP) plasma performance, as in the Tokamak, is strongly correlated with th...
The Advanced Limiter Test (ALT) project is the focus of a fruitful and intense International Energy ...
The heat load on plasma-facing components is a key issue for forthcoming fusion experiments. In this...
The existing 2-d two-fluid code for computing the plasma profiles in the scrape-off layer of limiter...
A heuristic model for the plasma scrape-off width balances magnetic drifts against parallel loss at ...
Large neutral gas accumulation has been observed in trapped volumes directly behind the mechanical l...
International audienceMotivated by Radio Frequency (RF) heating studies, the response of the plasma ...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, Fe...