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Particle exhaust studies in ASDEX Upgrade

Plasma Physics and Controlled Fusion, 1997
An experimental overview on pumping and particle exhaust studies for deuterium as well as for helium and neon in the ASDEX Upgrade divertor tokamak is presented. Strong turbomolecular pumps connected to the divertor region allow effective pumping of all these gases.
Bosch, H.   +14 more
openaire   +2 more sources

Divertor geometry optimization for ASDEX Upgrade

Journal of Nuclear Materials, 1997
Abstract One of the critical questions to be solved for ITER (or any other reactor) is the power exhaust problem (compatible with particle exhaust). Optimized divertors have to be tested in existing geometries based mainly on the idea of closing them very efficiently to the main chamber and, by the choice of the plate and baffle geometry, positively ...
Schneider, R.   +5 more
openaire   +2 more sources

The tungsten experiment in ASDEX Upgrade

Journal of Nuclear Materials, 1997
Abstract Tungsten coated tiles, manufactured by plasma spray on graphite, were mounted in the divertor of the ASDEX Upgrade tokamak and cover almost 90% of the surface facing the plasma in the strike zone. Over 500 plasma discharges, among which around 300 were heated with heating powers up to 10 MW, were performed up to now. The tungsten flux in the
Neu, R.   +16 more
openaire   +2 more sources

Quiescent regions below the X-point in ASDEX upgrade

Plasma Physics and Controlled Fusion, 2021
Probe measurements of plasma fluctuations in the divertor region of ASDEX Upgrade reveal the existence of two quiescent regions close to the separatrix: one on the low field side scrape-off layer and one on the high field side of the private flux region.
R. D. Nem   +8 more
semanticscholar   +1 more source

ASDEX UPGRADE POWER SUPPLY SYSTEM

1986
ASDEX Upgrade, the successor to the ASDEX device, is a new tokamak now under construction at Garching [1]. This experiment has a reactor-like divertor with the divertor coils located outside the toroidal field coils. This makes the power and energy requirements high since the total number of ampere-turns of the multipole coils increases approximately ...
Blaumoser, M.   +3 more
openaire   +2 more sources

ICRF system enhancements at ASDEX upgrade

Fusion Engineering and Design, 2001
The ion cyclotron range of frequency (ICRF) heating system at the tokamak ASDEX Upgrade has been in operation since 1991. It still continues to be modified in order to improve its efficiency, flexibility and reliability and to meet changing physics demands.
Braun, F.   +6 more
openaire   +3 more sources

ASDEX UPGRADE OHMIC HEATING CIRCUIT

1986
The OH system of ASDEX Upgrade provides a maximum flux swing of 9.5 Wb and a maximum plasma breakdown voltage of 35 V. The corresponding OH coil data are 50 kA and 30 kV.
Blaumoser, M.   +4 more
openaire   +2 more sources

B2-Eirene modelling of ASDEX Upgrade

Journal of Nuclear Materials, 1997
Abstract The extension of the computational region of the coupled fluid plasma, Monte-Carlo neutrals code, B2-Eirene, to the plasma center is discussed. The simulation of completely detached H-mode plasma is presented, as is the modelling of He and Ne compression.
Coster, D.   +11 more
openaire   +2 more sources

Recent ECRH results in ASDEX Upgrade

Electron Cyclotron Emission and Electron Cyclotron Heating, 2003
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Leuterer F   +19 more
openaire   +3 more sources

Ion orbit loss current in ASDEX Upgrade

Plasma Physics and Controlled Fusion, 1998
The orbit loss current is calculated for the ASDEX Upgrade geometry using the 5D (3D in configuration space and 2D in velocity space) Monte Carlo code ASCOT. The balance between the obtained current and the analytical estimate of the return current shows an L-H transition for the normalized collision frequency υ*i≈1 as expected from analytic theory ...
Heikkinen, J.   +7 more
openaire   +2 more sources

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