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The tungsten divertor experiment at ASDEX Upgrade
Plasma Physics and Controlled Fusion, 1996Tungsten-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
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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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Recent ECRH results in ASDEX Upgrade
Electron Cyclotron Emission and Electron Cyclotron Heating, 2003___
Leuterer F +19 more
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Experience with the ECRH system of ASDEX-Upgrade
Fusion Engineering and Design, 2001The 140 GHz ASDEX-Upgrade ECRH system uses four gyrotrons to generate a total power of 2 MW in a Gaussian beam for 2 s. External magnetic perturbations, originating from the poloidal stray magnetic field of the tokamak air core transformer, and also from the cryomagnet of the adjacent gyrotron, influence the startup of the oscillation and the electron ...
Leuterer, F. +18 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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ASDEX UPGRADE: THE FIRST PERIOD OF OPERATION
1993The first plasma in ASDEX Upgrade (AUG) was produced on 21stMarch '91 after more than 8 years of design, manufacture, and assembly. During the first operational period until August '92, with 1949 shots, the control and safety systems were commissioned in parallel with plasma discharges. Most discharges were run with He, but also H and D discharges were
Streibl, B. +32 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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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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The RF system and matching procedure for ASDEX and ASDEX upgrade
Fusion Engineering and Design, 1994Abstract The ICRH system outline of both the former ASDEX and the present ASDEX Upgrade experiment is described with regard to the matching procedure. The matching experience gained from the operation of ICRH on ASDEX lead to improvements in the ICRH operation on ASDEX Upgrade.
Hofmeister, F., Braun, F., Wesner, F.
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POSITION AND SHAPE CONTROL ON ASDEX-UPGRADE
1993ASDEX Upgrade utilizes a feedback control system for the plasma current, position and shape, which is novel in its approach to control local and global equilibrium parameters, its algorithm for the determination of the plasma equilibrium (via a function parameterization technique from magnetic measurements), its fully digital implementation, and its ...
Gruber, O. +7 more
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