No abstract available

No abstract available

[en] In this paper we report on experiments performed to investigate the retainment capability of the divertor for gaseous recycling impurities and for metallic impurities produced by sputtering at the neutralizer plates. For quantitative analyses the experiments are simulated by a one dimensional transport code, including a simple divertor model. (orig./GG)

[en] This report deals with investigations of plasma confinement carried out on the ASDEX divertor tokamak. It is comprised of two sections: The first section deals with the study of the condinement degradation in auxiliary heated sicharges; in the second section a regime will be described where the severe deterioration of the confinement quality at high heating power is avoided. This regime is called the H-mode because of the high confinement characteristics in contrast to the low confinement L-mode. There is evidence that the L-mode characteristics will not lead to sufficient confinement quality for successful plasma burning. The H-mode was observed for the first time on ASDEX. At present it is considered as the confinement regime with the best prospects for future tokamak operation. But both the study of L- and H-mode confinement physics have increased our understanding on energy transport in tokamaks. (orig./GG)

[en] The paper describes the design, manufacture and testing of water-cooled calorimeter panels of copper-chromium-zirconium alloy. The panels are employed in neutral beam injectors of nuclear fusion experiments for the absorption of high-energetic hydrogen beams. The maximum thermal power density is 2.75 kW/cm² and a maximum of 430 kW per panel can be dissipated. The individual parts of the panel are joined by high-temperature brazing and electron beam welding. (orig.)

[en] The fusion experiment ASDEX Upgrade, carried out at the Max-Planck-Institute for Plasma Physics (IPP) in Garching, is described. The aim of this experiment is to investigate a divertor, physically and technically, under reactor conditions. 7 figs

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No abstract available

[en] Published in summary form only

[en] The tilt angle of turbulent structures stands for the anisotropy of turbulence which is essential for understanding the dynamics of magnetized plasmas. It is a quantity predicted by theory and simulations, that provides information on the interplay between turbulence, micro-instabilities and plasma flows. A new method for measuring the tilt angle of turbulent structures in the core region of fusion plasmas using Doppler reflectometry is presented. First measurements of this type on the ASDEX Upgrade tokamak have shown a significant difference of tilt angle for different plasma conditions. The dominance of sheared flows in determining the structure tilt is experimentally demonstrated for different turbulence regimes. (letter)