A5101730561- Particle accelerators and beam dynamics
- Magnetic confinement fusion research
- Plasma Diagnostics and Applications
- Particle Accelerators and Free-Electron Lasers
- Superconducting Materials and Applications
- Gyrotron and Vacuum Electronics Research
- Fusion materials and technologies
- Atomic and Molecular Physics
- Muon and positron interactions and applications
- Ionosphere and magnetosphere dynamics
- High-Energy Particle Collisions Research
- Physics and Engineering Research Articles
- Atomic and Subatomic Physics Research
- Particle physics theoretical and experimental studies
- Mass Spectrometry Techniques and Applications
- Nuclear Physics and Applications
- Quantum Chromodynamics and Particle Interactions
- Ion-surface interactions and analysis
- Optics and Image Analysis
- Electromagnetic Compatibility and Measurements
- Advanced Theoretical and Applied Studies in Material Sciences and Geometry
- Dust and Plasma Wave Phenomena
- Solar Radiation and Photovoltaics
- Scientific Research and Discoveries
- Probiotics and Fermented Foods
Max Planck Institute for Plasma Physics
2012-2021
Max Planck Society
2008-2020
Fusion for Energy
2019
National Institutes for Quantum Science and Technology
2019
ITER
2019
National Institute for Fusion Science
2019
Institute of Plasma Physics
2018
Max Planck Innovation
2002-2017
Institute for Plasma Research
2011
ift Rosenheim
1998
The development of a large-area RF source for negative hydrogen ions, an official EFDA task agreement, is aiming at demonstrating ITER-relevant ion parameters. This implies current density 200 A m−2 accelerated D− ions filling pressure ⩽0.3 Pa and electron-to-ion ratio ⩽1 from extraction area similar to the positive-ion based sources JET ASDEX Upgrade pulse lengths up 1 h. work progressing along three lines in parallel: (i) optimization densities low electron/ion ratio, utilizing small areas...
The development of negative hydrogen ion sources for neutral beam systems is closely linked with an optimization formation in plasmas, which requires knowledge the plasma parameters. Emission spectroscopy introduced as a non-invasive and situ diagnostic tool line sight averaged Diagnostic lines simplified analysis methods variety parameters, such electron density temperature, gas atomic molecular density, caesium densities (atoms ions), are identified prepared direct application. Emphasis...
The ITER Neutral Beam Test Facility (NBTF), called PRIMA (Padova Research on Megavolt Accelerator), is hosted in Padova, Italy and includes two experiments: MITICA, the full-scale prototype of heating neutral beam injector, SPIDER, full-size radio frequency negative-ions source. NBTF realization exploitation SPIDER MITICA have been recognized as necessary to make future operation injectors efficient reliable, fundamental achievement thermonuclear-relevant plasma parameters ITER. This paper...
The ITER neutral beam system will be equipped with radio-frequency (RF) negative ion sources, based on the IPP Garching prototype source design. Up to 100 kW at 1 MHz is coupled RF driver, out of which plasma expands into main chamber. Compared arc driven sources are maintenance free and without evaporation tungsten. modularity driver concept permits supply large volumes. (one driver) demonstrated operation in hydrogen deuterium up one hour relevant parameters. ELISE test facility operating...
The ITER project requires additional heating by two neutral beam injectors, each accelerating to 1 MV a 40 A of negative deuterium ions, deliver the plasma power about 17 MW for one hour. As these requirements have never been experimentally met, it was recognized as necessary setup test facility, PRIMA (Padova Research on Megavolt Accelerator), in Italy, including full-size ion source, SPIDER, and prototype whole injector, MITICA, aiming develop injectors be installed ITER. This realization...
Abstract The ASDEX Upgrade (AUG) programme is directed towards physics input to critical elements of the ITER design and preparation operation, as well addressing issues for a future DEMO design. Since 2015, AUG equipped with new pair 3-strap ICRF antennas, which were designed reduction tungsten release during operation. As predicted, factor two on ICRF-induced W plasma content could be achieved by sheath voltage at antenna limiters via compensation image currents central side straps in...
For heating and current drive the neutral beam injection (NBI) system for ITER requires a 1 MeV deuterium up to h pulse length. In order inject required 17 MW large area source (1.9 m × 0.9 m) has deliver 40 A of negative ion at specified pressure 0.3 Pa. 2007, IPP RF driven hydrogen was chosen by board as new reference NBI due to, in principle, its maintenance free operation progress development. The performance analysis sources is strongly supported an extensive diagnostic program...
IPP Garching has successfully developed a RF-driven negative ion source for the ITER neutral beam injection system. The RF is now an interesting alternative to reference design with filamented sources due its in principle maintenance-free operation. Current densities of 330 A m−2 and 230 have been achieved hydrogen deuterium, respectively, at pressure 0.3 Pa electron/ion ratio 1 small extraction area (7.0 × 10−3 m2) short pulses (<4 s). Reliable deuterium operation more than 150 required...
For heating and current drive the neutral beam injection system for ITER requires a deuterium with an energy of 1 MeV up to h. In order inject required 17 MW ion source has deliver 40 A negative current. accelerated density 200 m−2 at specified pressure 0.3 Pa extraction area is 0.2 m2 resulting in large 1.5 × 0.6 m2. Two types sources have been under discussion, filamented arc inductively driven RF source, latter now having chosen reference design. The development sources, which fulfil...
Recent experiments at ASDEX Upgrade have achieved advanced scenarios with high βN (>3) and confinement enhancement over ITER98(y, 2) scaling, HH98y2 = 1.1–1.5, in steady state. These discharges been obtained a modified divertor configuration for Upgrade, allowing operation higher triangularity, changed neutral beam injection (NBI) system, more tangential, off-axis deposition. The figure of merit, βNHITER89-P, reaches up to 7.5 several seconds plasmas approaching stationary conditions....
Large and powerful negative hydrogen ion sources are required for the neutral beam injection (NBI) systems of future fusion devices. Simplicity maintenance-free operation favors RF sources, which developed intensively at Max-Planck-Institut für Plasmaphysik (IPP) since many years. The ions generated by caesium-enhanced surface conversion atoms positive on plasma grid surface. With a small scale prototype high current density low fraction co-extracted electrons pressure as well stable pulses...
The Max-Planck-Institut für Plasmaphysik test facility ELISE is an important intermediate step towards the in-time realization of ITER neutral beam injection system (NBI). equipped with a large radio-frequency (RF) driven negative hydrogen ion source (1 × 0.9 m2) half size NBI source. paper reports on main results very first operation caesium, but low RF power, both for and deuterium, pulse lengths up to 500 s. are rather encouraging achievement required parameters, especially in hydrogen,...
SPIDER is one of the two projects ITER Neutral Beam Test Facility (NBTF) under construction in Padova, Italy, at Consorzio RFX premises; it will have a 100 keV beam source with full-size prototype radiofrequency (RF) ion for Injector (NBI), designed to operate pulse length up 3600 s, featuring ITER-like filter field configuration, caesium oven layout and wide set diagnostics.These features allow reproducing operation like as cannot be done any other existing test facility.SPIDER realization...
The large-scale RF-driven ion source of the test facility extraction from a large experiment is aimed to deliver an accelerated current 20 A D− (23 H−) with extracted electron-to-ion ratio below one for up 1 h. Since first plasma pulses s in volume operation early 2013, followed by caesiation source, substantial progress has been achieved extending pulse length and RF power. record hydrogen are stable 400 18.3 at 180 kW total power 9.3 80 For deuterium pulse, limited amount co-extracted electrons.
The test facility ELISE represents an important step in the European R&D roadmap towards neutral beam injection (NBI) systems on ITER. provides early experience with operation of large radio frequency (RF) driven negative hydrogen ion sources. Starting first plasma pulses March 2013, has demonstrated stable 1 h discharges repetitive 10 s extraction every 3 min and deuterium at pressure 0.3 Pa required by Stable currents 9.3 A 5.8 have been extracted using only one quarter available RF power...
In negative hydrogen ion sources a too high amount or rapid increase in co-extracted electrons can prevent achieving the required current density and restrict pulse duration. One important measure for reducing stabilizing electron is magnetic filter field. The half-ITER-size NNBI test facility ELISE—in which field created by flowing through extraction system—is used performing experiments on reaction of source performance modifying topology; external magnet bars are attached to different...
The development of a radio frequency (RF) driven source for negative hydrogen ions the neutral beam heating devices fusion experiments has been successfully carried out at IPP since 1996 on test facility BATMAN. required ITER parameters have achieved with prototype consisting cylindrical driver back side racetrack like expansion chamber. extraction system, called "Large Area Grid" (LAG) was derived from positive ion accelerator ASDEX Upgrade (AUG) using its aperture size (ø 8 mm) and pattern...