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ECRH experiments in ASDEX upgrade

Fusion Engineering and Design, 2001
Abstract Modulated Electron Cyclotron Resonance Heating was applied in ASDEX Upgrade to study the electron heat diffusivity χ e . Its dependence on the isotope mass was found to be opposite to that one known from the power balance analysis. Off-axis ECRH deposition leads to a reduced electron heat transport in the centre which cannot be explained ...
Leuterer, F.   +7 more
openaire   +2 more sources

Arcing in ASDEX-Upgrade

Contributions to Plasma Physics, 1994
AbstractArc traces and luminous phenomena at the divertor tiles of ASDEX‐Upgrade were recorded, and experimentally modelled by artificially ignited arcs. At the graphite surfaces the arcs produced relatively immobile spots that were uniformly distributed in toroidal direction.
Juttner, B., Büchl, K., Weinlich, M.
openaire   +3 more sources

Study of runaway electron dynamics at the ASDEX Upgrade tokamak during impurity injection using fast hard x-ray spectrometry

Nuclear Fusion, 2021
To study the runaway electron (RE) dynamics during plasma discharge and develop scenarios for disruption mitigation, a hard x-ray (HXR) spectrometric system has been developed and commissioned at the ASDEX Upgrade tokamak (AUG).
A. Shevelev   +22 more
semanticscholar   +1 more source

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

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

The ECRH system of ASDEX Upgrade

Fusion Engineering and Design, 2001
Abstract The ECRH system of ASDEX Upgrade is now completed. Four gyrotrons generate a total Gaussian beam power of 2 MW/2 s at 140 GHz. The power is transmitted partly quasioptically and partly via corrugated HE-11 waveguides. The transmission line losses, determined calorimetrically, are about 12%.
F Leuterer, A Chirkov, K Kirov
exaly   +3 more sources

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

A centrifuge pellet injector for ASDEX upgrade

Vacuum, 1990
Abstract Plasma fuelling by pellet injection with deep particle deposition improves the plasma performance. Stationary conditions can be achieved with pellet frequencies of the order of 10 pellets per second. For medium-size experiments a centrifuge will be a suitable candidate that avoids the high gas flux of pneumatic guns. The pellet velocity will
Andelfinger, C.   +4 more
openaire   +2 more sources

The tungsten divertor experiment at ASDEX Upgrade

Plasma Physics and Controlled Fusion, 1996
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 600 plasma discharges have been performed to date, around 300 of which were auxiliary heated with heating powers up to 10 MW. The production of tungsten
Neu, R.   +126 more
openaire   +2 more sources

TECHNICAL FEATURES AND PROGRESS OF ASDEX UPGRADE

1986
The objective of ASDEX Upgrade is to investigage open poloidal divertor configurations as produced by a reactor-compatible, poloidal field coil system. The accessible poloidal and toroidal fields and hence the plasma current provide a sufficiently large plasma parameter regime to ensure the functioning of the open divertor.
Köppendörfer, W.   +30 more
openaire   +2 more sources

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