A5060850065- Magnetic confinement fusion research
- Ionosphere and magnetosphere dynamics
- Solar and Space Plasma Dynamics
- Nuclear reactor physics and engineering
- Superconducting Materials and Applications
- Fusion materials and technologies
- Meteorological Phenomena and Simulations
- Laser-Plasma Interactions and Diagnostics
- Laser-induced spectroscopy and plasma
- Computational Fluid Dynamics and Aerodynamics
- Fluid Dynamics and Turbulent Flows
- Particle accelerators and beam dynamics
- GNSS positioning and interference
- Geomagnetism and Paleomagnetism Studies
- Plasma Diagnostics and Applications
- Nuclear Engineering Thermal-Hydraulics
- Atomic and Molecular Physics
- Nuclear Physics and Applications
- Reservoir Engineering and Simulation Methods
- Modeling, Simulation, and Optimization
- Spacecraft and Cryogenic Technologies
- Geophysics and Gravity Measurements
Max Planck Institute for Plasma Physics
2018-2025
Max Planck Society
2018-2021
Forschungszentrum Jülich
2018
Self-consistent full-size turbulent-transport simulations of the divertor and SOL existing tokamaks have recently become feasible. This enables direct comparison turbulence against experimental measurements. In this work, we perform a series diverted Ohmic L-mode discharges on TCV tokamak, building first-of-a-kind dataset for validation edge models. dataset, referred to as TCV-X21, contains measurements from 5 diagnostic systems -- giving total 45 1- 2-D observables in two toroidal magnetic...
Abstract We report on developments in the edge and scrape-off-layer turbulence code GRILLIX to self-consistently simulate plasma coupled a fluid neutral gas model. The neutrals model is extended from single moment (neutrals density) three moments, describing additionally dynamics of parallel momentum pressure. employs flux-coordinate-independent (FCI) approach, wherein mesh neither conformal wall nor magnetic field. A new flux evaluation method consistent with FCI allows for implementing...
Abstract Small magnetic fluctuations ( <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:msub> <mml:mi>B</mml:mi> <mml:mn>1</mml:mn> </mml:msub> <mml:mrow> <mml:mo>/</mml:mo> </mml:mrow> <mml:mn>0</mml:mn> <mml:mo>∼</mml:mo> <mml:msup> <mml:mn>10</mml:mn> <mml:mo>−</mml:mo> <mml:mn>4</mml:mn> </mml:msup> </mml:math> ) are intrinsically present in a confinement plasma due to turbulent currents. While the perpendicular transport of particles and heat is typically...
Turbulent dynamics in the scrape-off layer (SOL) of magnetic fusion devices is intermittent with large fluctuations density and pressure. Therefore, a model required that allows perturbations similar or even larger magnitude to time-averaged background value. The fluid-turbulence code GRILLIX extended such global model, which consistently accounts for variation plasma parameters. Derived from drift reduced Braginskii equations, new includes electromagnetic electron-thermal dynamics, retains...
Abstract Turbulence simulations in diverted geometry across the edge and scrape-off layer (SOL) of ASDEX Upgrade are performed with GRILLIX code (Stegmeir et al 2019 Phys. Plasmas 26 052517). The underlying global (full- f ) drift-reduced Braginskii model allows to concurrently study self-consistent dynamics turbulence background as well evolution toroidal zonal flows. Different contributions radial electric field identified. dominant contribution on closed flux surfaces comes from ion...
Abstract The design of commercially feasible magnetic confinement fusion reactors strongly relies on the reduced turbulent transport in plasma edge during operation high mode (H-mode). We present first global turbulence simulations ASDEX Upgrade tokamak and scrape-off layer ITER baseline H-mode conditions. Reasonable agreement with experiment is obtained for outboard mid-plane measurements density, electron ion temperature, as well radial electric field. heat underpredicted by roughly 1/3....
To make predictions for and design fusion reactors, a multitude of physical processes must be considered. In the edge scrape-off layer (SOL), turbulent fluctuations intertwine with plasma background, which is largely determined by neutral gas, magnetic geometry plays an important role. A diffusive neutrals model has now been implemented in global Braginskii turbulence code GRILLIX. The based on flux-coordinate independent (FCI) approach, allows efficient simulations diverted equilibria. We...
Understanding and predicting turbulence in the edge scrape-off layer (SOL) is critical for optimization of magnetic confinement fusion devices. While there has been progress along these lines, especially with help fluid codes, development full-f electromagnetic gyrokinetic codes SOL, general, diverted geometries, remains crucial. In this work, we present simulations SOL ASDEX Upgrade tokamak novel grid-based (continuum) code GENE-X. The presented are performed at both reduced realistic...
Abstract Multi-spectral imaging of helium atomic emission (HeMSI) has been used to create 2D poloidal maps <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:msub> <mml:mrow> <mml:mi>T</mml:mi> </mml:mrow> <mml:mi mathvariant="normal">e</mml:mi> </mml:msub> </mml:math> and <mml:mi>n</mml:mi> in TCV’s divertor. To achieve these measurements, MANTIS multispectral cameras (Perek et al 2019 Rev. Sci. Instrum. 90 123514) simultaneously imaged four He I lines (two...
Abstract A recently developed reduced model of H-mode sustainment based on interchange-drift-Alfvén turbulence description in the vicinity separatrix matching experimental observations ASDEX Upgrade has been extended to experiments with unfavorable <?CDATA $\nabla B$?> <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:mi mathvariant="normal">∇</mml:mi> <mml:mi>B</mml:mi> </mml:mrow> </mml:math> drift. The combination theory magnetic-shear-induced...
Understanding and predicting turbulent transport in the edge scrape-off-layer (SOL) of magnetic confinement fusion devices is crucial for developing feasible power plants. In this work, we present latest improvements to gyrokinetic turbulence code GENE-X validate extended model against experimental results TCV tokamak (“TCV-X21”). features a full-f electromagnetic specifically targeted SOL simulations diverted geometries. can effect collisions using either basic Bhatnagar–Gross–Krook (BGK)...
Recent experiments from the Experimental Advanced Superconducting Tokamak (EAST) show that lower hybrid waves (LHWs) can profoundly change magnetic topology by inducing helical current filaments flowing along field lines in scrape-off layer. Here, it is investigated for first time how these perturbations caused LHWs affect edge plasma transport utilizing three-dimensional Monte Carlo code EMC3-EIRENE, both double-null and single-null configurations. The 3D structure reflected properties, due...
The appearance of blobs, filamentary structures featuring large intermittent perturbations, is characteristic for the scrape-off layer magnetic fusion devices. Therefore, a global model, which does not rely on assumptions about fluctuation level, necessary to model blobs accurately. Whereas GRILLIX, 3D fluid turbulence code, originally designed handle complex geometries via flux-coordinate independent approach, analysis here focuses thorough verification, validation, and identification basic...
The Landau-fluid closure for parallel heat fluxes is implemented in the edge turbulence fluid code GRILLIX, replacing previously used collisional Braginskii (with limiters). This extends validity of model toward lower collisionality, introduces non-local effects, and leads to a more realistic self-consistent limiting fluxes. Turbulence simulations comparing with divertor geometry are carried out. Clear differences between observed, most pronounced spurious up-down ion temperature asymmetry...
The design of commercially feasible magnetic confinement fusion reactors strongly relies on the reduced turbulent transport in plasma edge during operation high mode (H-mode). We present first global turbulence simulations ASDEX Upgrade tokamak and scrape-off layer (SOL) ITER baseline H-mode conditions. Reasonable agreement with experiment is obtained for outboard mid-plane measurements density, electron ion temperature, as well radial electric field. heat underpredicted by roughly a factor...
The understanding and the predictive capability for turbulence in plasma edge scrape-off layer (SOL) are crucial development of magnetic confinement fusion reactors. To this end, we characterise turbulent transport across SOL diverted ASDEX Upgrade tokamak attached L-mode conditions by means validated, global simulations. collisionality is controlled divertor neutrals density, as their ionisation increases density decreases temperature. radial E×B particle heat transport, quantified...
Abstract GRILLIX employs the flux‐coordinate independent approach (FCI), which allows us to study boundary plasma turbulence in realistic diverted configurations. Recently, physical model has been extended a global drift‐reduced Braginskii model, without any separation between background and fluctuations. It includes electromagnetic thermal dynamics with hot ions, relaxation of Boussinesq approximation non‐linear parametric dependencies. This contribution presents solutions associated...
We report on synthetic helium beam emission spectroscopy (BES) in fusion edge plasmas, as enabled by the 3D kinetic (neutral particle) transport code EIRENE.We also review and upgrade underlying atomic data base, resorting to most recent version of Goto-Fujimoto collisional-radiative a recommended publicly exposed reference cross section set from an internationally coordinated (IAEA) evaluation activity.On example Wendelstein 7-X (W7-X) stellarator, we use both upgraded base simulate...
The role of turbulence in setting boundary plasma conditions is presently a key uncertainty projecting to fusion energy reactors. To robustly diagnose edge turbulence, we develop and demonstrate technique translate brightness measurements HeI line radiation into local fluctuations via novel integrated deep learning framework that combines neutral transport physics collisional radiative theory for the 33D - 23P transition atomic helium with unbounded correlation constraints between electron...
Abstract Advanced divertor configurations modify the magnetic geometry of to achieve a combination strong flux expansion, increased connection length and higher volume—to improve detachment stability, neutral/impurity confinement heat‐channel broadening. In this paper, we discuss modification flux‐coordinate independent (FCI) turbulence code GRILLIX treat generalized geometry, allow for investigation effect on turbulent structures in edge scrape‐off layer (SOL). The development grids...
Abstract The temperature decay length ( <?CDATA $\lambda_{T_{\mathrm{e}}}$?> <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:msub> <mml:mi>λ</mml:mi> <mml:mrow> <mml:mi>T</mml:mi> <mml:mi mathvariant="normal">e</mml:mi> </mml:mrow> </mml:msub> </mml:math> ) in the near scrape-off layer (SOL) reflects ratio between transport parallel to magnetic field lines via Spitzer–Härm electron conduction and perpendicular mechanisms involving neoclassical anomalous...
Abstract A novel approach for estimating turbulent transport coefficients in fusion devices is presented. The diagnostic method established on the analysis of conditional variance one-point time series density or temperature fluctuations. It tested data obtained from probe measurements edge tokamak ASDEX Upgrade and stellarator Wendelstein 7-X, gyrofluid model GEMR. demonstrates a remarkable degree accuracy, typically within factor two actual measured by more difficult means. In particular,...