Power transport to the PDX graphite scoop limiter was measured during both ohmic- and neutral-beam-heated discharges by observing its front face temperatures using an infrared camera. Measurements were made as a function of plasma density, current, position, fueling mode, and heating power for both co- and counter-neutral beam injection. The measured thermal load on the scoop limiter was 25 to 50% of the total plasma heating power. The measured peak front face midplane temperature was 1500/sup 0/C corresponding to a peak surface power density of 3 kW/cm/sup 2/. This power density implies an effective parallel power flow of 54 kW/cm/sup 2/ in agreement with the radial power distribution extrapolated from TVTS and calorimetry measurements. Sy...
WEST is a full W tokamak with an extensive set of diagnostics for heat load measurements especially ...
A survey of the dependence of power balance on input power, shape, and plasma current was conducted ...
International audienceThe peak power flux densities from plasma ion bombardment on tokamak armor sur...
A particle scoop limiter with a graphite face backed by a 50 liter volume for collecting particles w...
This paper describes the use of novel combined Langmuir-calorimeter probes to measure edge plasma co...
The change in the temperature distribution was investigated for different target materials by insert...
The knowledge of edge plasma transport parameters and plasma edge phenomena is a key element in the ...
The heating efficiency of high power (up to 7.2 MW) near-perpendicular neutral beam injection in the...
Plasma profile data, from a number of neutral beam heated discharges in the START spherical tokamak,...
The PDX divertor configuration has recently been converted from an open to a closed geometry to inhi...
Radial transport of ions during co- and counter-neutral beam heating in the PLT tokamak has been stu...
In TORE-SUPRA, actively cooled modular limiters (time constant = 2 s) covered with carbon have been ...
Measurements of the gas fueling characteristics of the PDX tokamak have been extended in parameter r...
In 1981, the joint ORNL/PPPL PDX neutral beam heating project succeeded in reliably injecting 7.2 MW...
The heat load on plasma-facing components is a key issue for forthcoming fusion experiments. In this...
WEST is a full W tokamak with an extensive set of diagnostics for heat load measurements especially ...
A survey of the dependence of power balance on input power, shape, and plasma current was conducted ...
International audienceThe peak power flux densities from plasma ion bombardment on tokamak armor sur...
A particle scoop limiter with a graphite face backed by a 50 liter volume for collecting particles w...
This paper describes the use of novel combined Langmuir-calorimeter probes to measure edge plasma co...
The change in the temperature distribution was investigated for different target materials by insert...
The knowledge of edge plasma transport parameters and plasma edge phenomena is a key element in the ...
The heating efficiency of high power (up to 7.2 MW) near-perpendicular neutral beam injection in the...
Plasma profile data, from a number of neutral beam heated discharges in the START spherical tokamak,...
The PDX divertor configuration has recently been converted from an open to a closed geometry to inhi...
Radial transport of ions during co- and counter-neutral beam heating in the PLT tokamak has been stu...
In TORE-SUPRA, actively cooled modular limiters (time constant = 2 s) covered with carbon have been ...
Measurements of the gas fueling characteristics of the PDX tokamak have been extended in parameter r...
In 1981, the joint ORNL/PPPL PDX neutral beam heating project succeeded in reliably injecting 7.2 MW...
The heat load on plasma-facing components is a key issue for forthcoming fusion experiments. In this...
WEST is a full W tokamak with an extensive set of diagnostics for heat load measurements especially ...
A survey of the dependence of power balance on input power, shape, and plasma current was conducted ...
International audienceThe peak power flux densities from plasma ion bombardment on tokamak armor sur...