A5003626188- Particle accelerators and beam dynamics
- Magnetic confinement fusion research
- Particle Accelerators and Free-Electron Lasers
- Superconducting Materials and Applications
- Plasma Diagnostics and Applications
- Fusion materials and technologies
- Gyrotron and Vacuum Electronics Research
- Ionosphere and magnetosphere dynamics
- Nuclear Physics and Applications
- Spacecraft and Cryogenic Technologies
- Nuclear reactor physics and engineering
- Atomic and Molecular Physics
- Quantum, superfluid, helium dynamics
- Particle Detector Development and Performance
- Atomic and Subatomic Physics Research
- Muon and positron interactions and applications
- Extraction and Separation Processes
- Rocket and propulsion systems research
- Laser-Plasma Interactions and Diagnostics
- High-pressure geophysics and materials
- Advanced Battery Technologies Research
- Nuclear and radioactivity studies
Max Planck Institute for Plasma Physics
2016-2025
Max Planck Society
2008-2021
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 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...
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...
The ITER neutral beam system requires a negative hydrogen ion of 48 A with an energy 0.87 MeV and deuterium 40 1 MeV. is extracted from large RF driven source the dimension 1.9 × 0.9 m 2 . An important role for transport ions to extractor suppression co-extracted electrons magnetic filter field in front extractor. For will be generated by current up 4 kA flowing through first grid extrapolation results obtained small IPP prototype source, where has different 3D structure as it permanent...
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...
Abstract Experiments on ASDEX Upgrade (AUG) in 2021 and 2022 have addressed a number of critical issues for ITER EU DEMO. A major objective the AUG programme is to shed light underlying physics confinement, stability, plasma exhaust order allow reliable extrapolation results obtained present day machines these reactor-grade devices. Concerning pedestal physics, mitigation edge localised modes (ELMs) using resonant magnetic perturbations (RMPs) was found be consistent with reduction linear...
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...
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...
Abstract The ASDEX Upgrade (AUG) programme, jointly run with the EUROfusion MST1 task force, continues to significantly enhance physics base of ITER and DEMO. Here, full tungsten wall is a key asset for extrapolating future devices. high overall heating power, flexible mix comprehensive diagnostic set allows studies ranging from mimicking scrape-off-layer divertor conditions DEMO at density fully non-inductive operation ( q 95 = 5.5, ) low density. Higher installed electron cyclotron...
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...
Abstract For the D-T operational phase of international fusion experiment ITER, starting in 2035, pulses are planned with Q > 10 and a duration 400 s = 5 for up to 3600 s. The two neutral beam injection (NBI) systems will deliver 33.3 MW heating power plasma also be an important source non-inductive current drive. An essential part NBI is large RF driven negative hydrogen or deuterium ions. In order fulfil requirements imposed system, ion has intense, stable homogeneous over pulse lengths...
The international fusion experiment ITER requires for the plasma heating and current drive a neutral beam injection system based on negative hydrogen ion sources at 0.3Pa. source must deliver of 40A D− up to 1h with an accelerated density 200A∕m2 ratio coextracted electrons ions below 1. extraction area is 0.2m2 from aperture array envelope 1.5×0.6m2. A high power rf-driven has been successfully developed Max-Planck Institute Plasma Physics (IPP) three test facilities in parallel. Current...
This instrument allows controlled evaporation of the alkali metal cesium over a wide range rates. The oven has three unique features. first is an reservoir that uses dispenser as source. heating current controls rate allowing generation adjustable and stable flow pure cesium. second blocking valve, which fully metallic body oven. construction both reduces contamination enables to be operated up 300 °C, with only small temperature variations (&lt;5 °C). By minimizing variation, built at...