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Dive into the research topics where F. Leuterer is active.

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Featured researches published by F. Leuterer.


Nuclear Fusion | 1999

Experiments on neoclassical tearing mode stabilization by ECCD in ASDEX Upgrade

H. Zohm; G. Gantenbein; G. Giruzzi; S. Günter; F. Leuterer; M. Maraschek; J. Meskat; A. G. Peeters; W. Suttrop; D. Wagner; M. Zabiégo

The reduction of neoclassical tearing modes by ECCD is demonstrated experimentally. It is shown that with an averaged ECCD power of only 4-8% of the total heating power injected into the discharge, the island width can be reduced by 40%, provided that the centre of deposition is very close to the resonant surface. The reduction in mode amplitude results in a partial recovery of the loss of stored energy induced by the mode. This experimental result is well reproduced by modelling calculations.


Nuclear Fusion | 2010

Comparison of fast ion collective Thomson scattering measurements at ASDEX Upgrade with numerical simulations

M. Salewski; F. Meo; M. Stejner; O. Asunta; Henrik Bindslev; V. Furtula; S. B. Korsholm; Taina Kurki-Suonio; F. Leipold; F. Leuterer; P. K. Michelsen; D. Moseev; S. K. Nielsen; J. Stober; G. Tardini; D. Wagner; P. Woskov

Collective Thomson scattering (CTS) experiments were carried out at ASDEX Upgrade to measure the one-dimensional velocity distribution functions of fast ion populations. These measurements are compared with simulations using the codes TRANSP/NUBEAM and ASCOT for two different neutral beam injection (NBI) configurations: two NBI sources and only one NBI source. The measured CTS spectra as well as the inferred one-dimensional fast ion velocity distribution functions are clearly asymmetric as a consequence of the anisotropy of the beam ion populations and the selected geometry of the experiment. As expected, the one-beam configuration can clearly be distinguished from the two-beam configuration. The fast ion population is smaller and the asymmetry is less pronounced for the one-beam configuration. Salient features of the numerical simulation results agree with the CTS measurements while quantitative discrepancies in absolute values and gradients are found.


Nuclear Fusion | 2008

Status of the new multi-frequency ECRH system for ASDEX Upgrade

D. Wagner; G. Grünwald; F. Leuterer; A. Manini; F. Monaco; M. Münich; H. Schütz; J. Stober; H. Zohm; T. Franke; M. Thumm; G. Gantenbein; R. Heidinger; A. Meier; W. Kasparek; C. Lechte; A. G. Litvak; G. G. Denisov; Alexei V. Chirkov; E. M. Tai; L. G. Popov; V.O. Nichiporenko; V. E. Myasnikov; E.A. Solyanova; S.A. Malygin; F. Meo; Paul P. Woskov

Summary form only given. The first two-frequency GYCOM gyrotron Odissey-1 has been installed and put into operation in the new multi-frequency ECRH system at the ASDEX Upgrade tokamak experiment. It works at 105 GHz and 140GHz with output power 610kW and 820kW respectively at a pulse length of 10s. A further extension of the system with 3 more gyrotrons is underway. These gyrotrons will be step-tunable and operate at two additional intermediate frequencies between 105 and 140GHz. Such gyrotrons will require broadband vacuum windows. Construction and cold tests of a first broadband double-disc toms window are completed. The transmission to the tonis is in normal air, through corrugated aluminum waveguides with I.D.=87mm over a total length of about 70m. Calorimetric measurements gave a total transmission loss of only 12% at 105GHz and 10% at 140GHz. The variable frequency will significantly extend the operating range of the ECRH system, e.g. allow for central heating at different magnetic fields. Other experimental features, like the suppression of neoclassical tearing modes (NTM), require to drive current on the high field side without changing the magnetic field. The stabilization of NTMs requires a very localized power deposition such that its center can be feedback controlled, for instance to keep it on a resonant q-surface. For this reason fast movable launchers have been installed.


Nuclear Fusion | 2007

Control of MHD Instabilities by ECCD: ASDEX Upgrade Results and Implications for ITER

H. Zohm; G. Gantenbein; F. Leuterer; A. Manini; M. Maraschek; Q. Yu

The requirements for control of MHD instabilities by electron cyclotron current drive (ECCD) are reviewed. It is shown that a localized current drive is needed for control of both sawteeth and neoclassical tearing modes (NTMs). In the case of NTMs, the deposition width should be smaller than the island width for efficient control. At island widths smaller than the deposition width, as is predicted to occur in ITER, theory suggests that efficient control is possible only by modulating the ECCD power in phase with the island. These predictions are experimentally confirmed in ASDEX Upgrade for NTM control. Narrow deposition has also been used to extend the operational range of NTM stabilization in ASDEX Upgrade to lower q95 and in the improved H-mode scenario. Our results suggest that, for the ITER ECCD system, good localization of the driven current profile as well as the capability to modulate the ECCD in phase with rotating modes will be needed for efficient MHD control by ECCD.


Nuclear Fusion | 2003

Electron heat transport in ASDEX Upgrade: experiment and modelling

F. Ryter; G. Tardini; F. De Luca; H.-U. Fahrbach; F. Imbeaux; A. Jacchia; K. Kirov; F. Leuterer; P. Mantica; A. G. Peeters; G. Pereverzev; W. Suttrop

The electron heat transport is investigated in ASDEX Upgrade using electron cyclotron heating (ECH) combining steady-state and power modulation schemes. Experiments in which the electron heat flux has been varied in the confinement region while the edge was kept constant were performed. They demonstrate that ∇ Te and ∇ Te/Te can be varied by a factor of 3 and 2, respectively. They allow a detailed determination of the transport characteristics by comparing steady-state and modulation data with modelling. The analyses clearly show the existence of a threshold (∇ Te/Te)crit above which transport increases. Both steady-state and modulation experiments agree with such a transport model. The experiments have been carried out at low density in the L-mode to ensure low electron–ion coupling and good conditions for studying electron heat transport. The experiments were carried out at two different values of plasma current and show that transport increases at low current, as well-known from global scaling laws for confinement time. In the pure off-axis cases the region inside the ECH deposition is just at the (∇ Te/Te)crit threshold, which allows it to be measured directly from the profile of ∇ Te/Te deduced from the experimental Te profile. Using this technique, it appears that the turbulence threshold agrees with that expected from the trapped electron mode driven turbulence. It has the correct absolute value and seems to have the correct radial dependence that is determined by the trapped electron fraction and by the density gradient. It almost does not vary with other plasma parameters. In contrast, the threshold calculated for electron temperature gradient modes is higher than the experimental values of ∇ Te/Te and this turbulence is therefore not expected to be excited under these experimental conditions.


Nuclear Fusion | 1991

Non-linear coupling of the lower hybrid grill in ASDEX

V.A. Petržílka; F. Leuterer; F. X. Söldner; L. Giannone; R. Schubert

Computations of the reflection coefficient based on a non-linear lower hybrid (LH) coupling theory are presented and compared with the measurements of the reflection coefficient of the ASDEX tokamak LH grill, where powers up to 4 kW/cm2 have been launched. This high LH power density modifies the electron density in front of the grill because of ponderomotive forces. Thus, the coupling and the power reflection coefficient change. To explain the observed saturation of the growth of the reflection coefficient with power, it is necessary to take into account some heating of the plasma in front of the grill by the transmitted LH power, which also leads to a poloidally inhomogeneous edge electron density.


Nuclear Fusion | 2000

Propagation of Cold Pulses and Heat Pulses in ASDEX Upgrade

F. Ryter; R. Neu; R. Dux; H.-U. Fahrbach; F. Leuterer; G. Pereverzev; J. Schweinzer; J. Stober; W. Suttrop; F. De Luca; A. Jacchia; J. E. Kinsey

Experiments on electron heat transport were performed in the tokamak ASDEX Upgrade, mainly in ohmically heated plasmas, applying either edge cooling with laser blow-off impurity injection or edge heat pulses with ECRH. Repetitive pulses within one plasma discharge were made allowing Fourier transformation of the temperature perturbation, yielding a good signal to noise ratio up to high harmonics and a detailed investigation of the pulse propagation. For densities lower than 1.8 × 1019m-3, an increase of central electron temperature was found as the response to edge cooling via impurity injection similar to observations made in the TEXT, TFTR, RTP and Tore Supra tokamaks. The inversion does not appear instantaneously, but with a time delay roughly compatible with diffusion. Modelling of the propagation of the cold pulses in the framework of the IFS-PPPL model yields qualitative agreement. However, the predicted increase of ion temperature is not observed experimentally on a fast timescale. The response to ECRH heat pulses is not perfectly symmetrical to cold pulse experiments, but the similarities suggest a common underlying physical mechanism. No inversion of the heat pulse is found, instead the initial pulse from the edge is associated with a second, much slower, heat pulse in the centre. This central reaction is in fact quite similar (and not symmetrical) to that of the cold pulses. By varying the position of the ECRH deposition it could be shown that the central increase is related to the arrival of the pulse close to the inversion radius and not to the initial pulse. Modelling was performed to investigate the possible physics mechanisms and for comparison with the cold pulses.


Review of Scientific Instruments | 2008

Commissioning activities and first results from the collective Thomson scattering diagnostic on ASDEX Upgrade (invited)

F. Meo; Henrik Bindslev; Søren Bang Korsholm; Vedran Furtula; F. Leuterer; F. Leipold; Poul Michelsen; Stefan Kragh Nielsen; M. Salewski; J. Stober; D. Wagner; P. Woskov

The collective Thomson scattering (CTS) diagnostic installed on ASDEX Upgrade uses millimeter waves generated by the newly installed 1 MW dual frequency gyrotron as probing radiation at 105 GHz. It measures backscattered radiation with a heterodyne receiver having 50 channels (between 100 and 110 GHz) to resolve the one-dimensional velocity distribution of the confined fast ions. The steerable antennas will allow different scattering geometries to fully explore the anisotropic fast ion distributions at different spatial locations. This paper covers the capabilities and operational limits of the diagnostic. It then describes the commissioning activities carried out to date. These activities include gyrotron studies, transmission line alignment, and beam pattern measurements in the vacuum vessel. Overlap experiments in near perpendicular and near parallel have confirmed the successful alignment of the system. First results in near perpendicular of scattered spectra in a neutral beam injection (NBI) and ion cyclotron resonance heating (ICRH) plasma (minority hydrogen) on ASDEX Upgrade have shown evidence of ICRH heating phase of hydrogen.


symposium on fusion technology | 2003

Plans for a new ECRH system at ASDEX Upgrade

F. Leuterer; K. Kirov; F. Monaco; M. Münich; H. Schütz; F. Ryter; D. Wagner; R. Wilhelm; H. Zohm; T. Franke; K. Voigt; M. Thumm; Roland Heidinger; G. Dammertz; K. Koppenburg; G. Gantenbein; H. Hailer; W. Kasparek; G. A. Müller; A. Bogdashov; G. G. Denisov; V. Kurbatov; A. Kuftin; A. Litvak; S. A. Malygin; E. Tai; V. Zapevalov

Abstract A new ECRH system is being constructed for ASDEX Upgrade with a total power of 4 MW, generated by four gyrotrons, and a pulse duration of 10 s. Particular features are the use of gyrotrons which can work at various frequencies in the range 104–140 GHz and correspondingly broad band transmission components. The transmission will be at normal air pressure, and at the torus we will have a tunable double disk vacuum window. A further aim is the installation of fast moveable mirrors for a feedback controlled localized power deposition.


International Symposium on Laser-Aided Plasma Diagnostics | 2010

First results and analysis of collective Thomson scattering (CTS) fast ion distribution measurements on ASDEX Upgrade

F. Meo; M. Stejner; M. Salewski; Henrik Bindslev; T. Eich; V. Furtula; Søren Bang Korsholm; F. Leuterer; F. Leipold; Poul Michelsen; D. Moseev; Stefan Kragh Nielsen; B. Reiter; J. Stober; D. Wagner; P. Woskov

Experimental knowledge of the fast ion physics in magnetically confined plasmas is essential. The collective Thomson scattering (CTS) diagnostic is capable of measuring localized 1D ion velocity distributions and anisotropies dependent on the angle to the magnetic field. The CTS installed at ASDEX-Upgrade (AUG) uses mm-waves generated by the 1 MW dual frequency gyrotron. The successful commissioning the CTS at AUG enabled first scattering experiments and the consequent milestone of first fast ion distribution measurements on AUG presented in this paper. The first fast ion distribution results have already uncovered some physics of confined fast ions at the plasma centre with off-axis neutral beam heating. However, CTS experiments on AUG H-mode plasmas have also uncovered some unexpected signals not related to scattering that required additional analysis and treatment of the data. These secondary emission signals are generated from the plasma-gyrotron interaction therefore contain additional physics. Despite their existence that complicate the fast ion analysis, they do not prevent the diagnostics capability to infer the fast ion distribution function on AUG.

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M. Thumm

Karlsruhe Institute of Technology

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W. Kasparek

University of Stuttgart

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