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Particle exhaust studies in ASDEX Upgrade
Plasma Physics and Controlled Fusion, 1997An 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
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Divertor geometry optimization for ASDEX Upgrade
Journal of Nuclear Materials, 1997Abstract 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
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The tungsten experiment in ASDEX Upgrade
Journal of Nuclear Materials, 1997Abstract 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
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Quiescent regions below the X-point in ASDEX upgrade
Plasma Physics and Controlled Fusion, 2021Probe 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
1986ASDEX 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
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ICRF system enhancements at ASDEX upgrade
Fusion Engineering and Design, 2001The 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
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ASDEX UPGRADE OHMIC HEATING CIRCUIT
1986The 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
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B2-Eirene modelling of ASDEX Upgrade
Journal of Nuclear Materials, 1997Abstract 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
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Recent ECRH results in ASDEX Upgrade
Electron Cyclotron Emission and Electron Cyclotron Heating, 2003___
Leuterer F +19 more
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Ion orbit loss current in ASDEX Upgrade
Plasma Physics and Controlled Fusion, 1998The 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
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