A strong effect of a moderately elevated surface temperature on net carbon deposition and deuterium co-deposition in the DIII-D divertor was observed under detached conditions. A graphite DiMES sample with a 2 mm wide, 18 mm deep gap lined with silicon catcher plates was exposed to lower-single-null (LSN) L-mode plasmas first at room temperature, and then pre-heated to 200 degrees C by a built-in electrical heater. At the elevated temperature, deuterium co-deposition in the gap was reduced by an order of magnitude. At the plasma-facing surface of the pre-heated sample net carbon erosion was measured at a rate of 3 nm s(-1), whereas without pre-heating net deposition is normally observed under detachment. In a related experiment three sets o...
Dedicated DIII-D experiments coupled with modeling reveal that the net erosion rate of high-Z materi...
Optical diagnostics in ITER will rely on mirrors near the plasma and the deterioration of the reflec...
Plasma disruptions are a serious concern in tokamak design because of the high impulsive heat loads ...
A strong effect of a moderately elevated surface temperature on net carbon deposition and deuterium ...
Net erosion rates of carbon target plates have been measured in situ for the DIII-D lower divertor. ...
The DiMES (Divertor Material Evaluation Studies) mechanism allows insertion of material samples to t...
The Divertor Materials Evaluation System (DiMES) at General Atomics has successfully advanced the un...
The exposure of ATG graphite sample to DIII-D divertor plasma was provided by the DiMES (Divertor Ma...
Metallic mirrors will be used in ITER for optical diagnostics working in different spectral ranges. ...
The DiMES (Divertor Material Evaluation Studies) mechanism allows insertion of material samples to t...
grantor: University of TorontoPieces of divertor and midplane tiles from DIII-D have been ...
Mirrors will be used in ITER in all optical diagnostic systems observing the plasma radiation in the...
Silicon samples were exposed in the scrape-off layer of the TEXTOR plasma using a fast reciprocating...
As High-Z materials will likely be used as plasma-facing components (PFCs) in future fusion devices,...
Optical diagnostics in ITER will rely on mirrors near the plasma and the deterioration of the reflec...
Dedicated DIII-D experiments coupled with modeling reveal that the net erosion rate of high-Z materi...
Optical diagnostics in ITER will rely on mirrors near the plasma and the deterioration of the reflec...
Plasma disruptions are a serious concern in tokamak design because of the high impulsive heat loads ...
A strong effect of a moderately elevated surface temperature on net carbon deposition and deuterium ...
Net erosion rates of carbon target plates have been measured in situ for the DIII-D lower divertor. ...
The DiMES (Divertor Material Evaluation Studies) mechanism allows insertion of material samples to t...
The Divertor Materials Evaluation System (DiMES) at General Atomics has successfully advanced the un...
The exposure of ATG graphite sample to DIII-D divertor plasma was provided by the DiMES (Divertor Ma...
Metallic mirrors will be used in ITER for optical diagnostics working in different spectral ranges. ...
The DiMES (Divertor Material Evaluation Studies) mechanism allows insertion of material samples to t...
grantor: University of TorontoPieces of divertor and midplane tiles from DIII-D have been ...
Mirrors will be used in ITER in all optical diagnostic systems observing the plasma radiation in the...
Silicon samples were exposed in the scrape-off layer of the TEXTOR plasma using a fast reciprocating...
As High-Z materials will likely be used as plasma-facing components (PFCs) in future fusion devices,...
Optical diagnostics in ITER will rely on mirrors near the plasma and the deterioration of the reflec...
Dedicated DIII-D experiments coupled with modeling reveal that the net erosion rate of high-Z materi...
Optical diagnostics in ITER will rely on mirrors near the plasma and the deterioration of the reflec...
Plasma disruptions are a serious concern in tokamak design because of the high impulsive heat loads ...