Results 111 to 120 of about 387 (143)
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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, M Munich, A Chirkov
exaly   +3 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   +3 more sources

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   +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

Tungsten erosion by arcs in ASDEX upgrade

Journal of Nuclear Materials, 2011
The transition from carbon to high-Z divertor devices reduces the erosion of the plasma facing components (PFC) strongly. Arcing as second erosion mechanism beside physical sputtering may now dominating the erosion. A procedure based on photographic techniques, profilometry and scanning electron microscopy was developed to investigate arc damage in ...
Rohde, V.   +8 more
openaire   +2 more sources

Routes to divertor detachment in ASDEX Upgrade

Journal of Nuclear Materials, 1997
Abstract A simple analytic model of divertor radiation is used as a framework for identifying different routes to divertor detachment. Three means of achieving detachment are demonstrated experimentally including, increasing plasma density, purposely increasing the impurity level and increasing the scrape-off layer connection length.
Pitcher, C.   +6 more
openaire   +2 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

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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