A5024522779- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Fusion materials and technologies
- Nuclear reactor physics and engineering
- Particle accelerators and beam dynamics
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Laser-induced spectroscopy and plasma
- Electromagnetic Launch and Propulsion Technology
- Ionosphere and magnetosphere dynamics
- Magnetic Field Sensors Techniques
- Spacecraft and Cryogenic Technologies
- Offshore Engineering and Technologies
- Non-Destructive Testing Techniques
- Particle Detector Development and Performance
- Vacuum and Plasma Arcs
- Body Composition Measurement Techniques
- Trace Elements in Health
- Engineering Applied Research
- Smart Grid Security and Resilience
- Nuclear and radioactivity studies
- Ship Hydrodynamics and Maneuverability
- Nuclear Engineering Thermal-Hydraulics
HUN-REN Centre for Energy Research
2021-2024
Hungarian Academy of Sciences
2024
ITER
2019-2021
HUN-REN Wigner Research Centre for Physics
2018-2019
Max Planck Institute for Plasma Physics
2019
Max Planck Society
2019
Institute for Particle and Nuclear Physics
2008-2011
Danube Research Institute
2007
The ITER Disruption Mitigation System (DMS) Support Laboratory at the Centre for Energy Research, Budapest, Hungary aims characterization of de-sublimation, acceleration and shattering cryogenic pellets, which will be fired upon request into plasma to mitigate detrimental consequences disruptions. test bench includes a fast-acting valve pellet acceleration, releases high-pressure gas on millisecond time scale. is new development since no market existed would have met requirements....
Diagnosing the density profile at edge of high temperature fusion plasmas by an accelerated lithium beam is a known technique since decades. By knowledge relevant atomic physics rate coefficients, plasma electron can be calculated from relatively calibrated light along beam. Several additional possibilities have already been demonstrated: Charge Exchange Resonance Spectroscopy (CXRS) for ion temperature/flow and Zeeman polarimetry current; therefore Li-beam diagnostic offers wealth...
ITER needs a Disruption Mitigation System (DMS) for protection from the consequences of plasma disruptions during high-power operation. The current DMS is based on Shattered Pellet Injection (SPI) technology. This works basic principle cryogenic pipe gun with around half-meter-long acceleration barrel. It important to avoid any contact between pellet and internal surfaces flight line minimize risk premature breakage. Therefore, dimensions tube SPI are relatively large compared hence...
Shattered Pellet Injection (SPI) is a common technique used in Disruption Mitigation Systems to prevent or minimize the effect of plasma disruptions Tokamaks. To operate an SPI system, fast-acting valve needed for accelerating pellets. An eddy current actuated high-pressure fast was developed 2021, dedicated system ITER DMS Support Laboratory at Centre Energy Research. Based on experiences operation, novel has been improve durability and reliability, while design simplified terms...
The imaging heavy ion beam probe (i-HIBP) developed at the ASDEX Upgrade tokamak is a new diagnostic concept for investigations edge of high temperature plasmas. By means alkali injector, neutral primary an energy 70 keV injected into fusion plasma, where it ionized generating fan secondary beams. These are deflected by magnetic field and intersect scintillator plate in limiter shadow tokamak. light pattern on detected with speed camera contains radial information density, electrostatic...
On a Wendelstein 7-X (W7-X), an alkali metal beam (AMB) diagnostic system was installed in order to measure the plasma edge electron density profiles and turbulence transport. A sodium injected plasma, light emission observed by optical system. During last operation phase, OP1.2b campaign trial spectral measurements were performed with dedicated branch. The results showed emergence of potential CX lines spectra during injection. identified as Carbon III, which dominant other diagnostics at...
Abstract Plasma filaments have been measured with alkali beam emission spectroscopy in the plasma edge, divertor island, and scrape-off layer of Wendelstein 7-X. Due to high intensity a 1–2 kHz mode, new, correlation based conditional averaging algorithm was used search for signals. With that method, effects different magnetic configurations density levels on filament properties are observed. In where islands small do not play an important role connection length topology, behave similar...
The analysis of the gas expansion in test bench ITER DMS Support Laboratory is discussed. For this purpose, numerical FEM simulations were performed during design phase laboratory. These are compared with experimental data, that have been obtained after construction was finished. and results found to agree well. Both indicate emergence pressure waves acceleration barrel. contribute pellet detachment from barrel wall. Supersonic velocities also observed simulations, an indirect indication for...
Measurements of ion temperature profiles are required to assess the energy and particle transport processes in Wendelstein 7-X stellarator. This device is equipped with a diagnostic alkali beam, which can be utilized determine local impurity temperatures densities by Charge Exchange Recombination Spectroscopy (CXRS). It could provide such edge plasma, where other diagnostics less efficient. With this contribution, first results CXRS measurements on sodium beam from scientific operation phase...
Abstract A support laboratory has been set up to study pellet production, launch and shattering of cryogenic protium, deuterium, neon pellets for the ITER disruption mitigation system, which plans use 28.5 × 57 mm (diameter length) an mixture in Shattered Pellet Injectors. Such large protium have not produced launched before, therefore desublimation process studied detail two steps. First 19 diameter were produced, followed by demonstration final size. recipes established all types, it was...
Diagnostics in ITER are supported by big structures called port plugs, the second main function of which is to ensure a sufficient shielding against neutrons and gammas. Regarding integration diagnostics equatorial new approach under study, consists installing "drawers". This paper describes recent work has been performed Europe on drawers Equatorial Port Plug 1 (EPP1). First methodology followed progress this plug described resulting arrangement shown. Then special attention paid two EPP1,...
ITER is a large-scale experimental nuclear fusion reactor currently under construction. To protect the first wall components of machine against damages due to plasma disruption event, needs Disruption Mitigation System (DMS). The DMS based on Shattered Pellet Injector (SPI) technology. One issues with SPI injection that propellant gas may overtake pellet and start edge cooling before material deposition by fragments takes place. Edge increase runaway electron generation, therefore should be...
Atomic beam probe is an extension of the routinely used emission spectroscopy diagnostic for plasma edge current fluctuation measurement at magnetically confined plasmas. Beam atoms ionized by are directed to a curved trajectory magnetic field and may be detected close wall device. The arrival location distribution ions carry information about distribution, density profile, electric potential in edge. This paper describes micro-Faraday cup matrix detector few microampere ion device...