A5005106718- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Nuclear reactor physics and engineering
- Solar and Space Plasma Dynamics
- Particle accelerators and beam dynamics
- Ionosphere and magnetosphere dynamics
- Laser-Plasma Interactions and Diagnostics
- Tribology and Lubrication Engineering
- Astronomy and Astrophysical Research
- Stellar, planetary, and galactic studies
- Spacecraft and Cryogenic Technologies
- Gas Dynamics and Kinetic Theory
- Astronomical Observations and Instrumentation
- Plasma Diagnostics and Applications
Forschungszentrum Jülich
2019-2025
University of Wisconsin–Madison
2022-2024
KU Leuven
2021-2024
Abstract Resilient divertor features connected to open chaotic edge structures in the Helically Symmetric eXperiment are investigated. For first time, an expanded vessel wall was considered that would give space for implementation of a physical target structure. The analysis done four different magnetic configurations with very plasma edges. A resilient interaction pattern identified across all configurations. This manifests as qualitatively similar footprint behavior equilibria. Overall,...
Abstract After a long device enhancement phase, scientific operation resumed in 2022. The main new components are the water cooling of all plasma facing and water-cooled high heat flux divertor units. Water allowed for first long-pulse campaign. A maximum discharge length 8 min was achieved with total heating energy 1.3 GJ. Safe demonstrated attached detached mode. Stable detachment is readily some magnetic configurations but requires impurity seeding small pitch angle within edge islands....
Within the EUROfusion MST1 work package, a series of experiments has been conducted on AUG and TCV devices to disentangle role plasma fueling shape for onset small ELM regimes. On both devices, regimes with high confinement are achieved if only two conditions fulfilled at same time. Firstly, density separatrix must be large enough (), leading pressure profile flattening separatrix, which stabilizes type-I ELMs. Secondly, magnetic configuration close double null (DN), reduction shear in...
Abstract The design of divertor targets and baffles for optimal heat particle
exhaust from magnetically confined fusion plasmas requires a combination fast,
low-fidelity models (such as EMC3-Lite [1]) scoping studies high-fidelity ones
(such EMC3-EIRENE [2]) verification. Both those approaches benefit a
magnetic flux tube mesh fast interpolation mapping field line segments [3]. A
new automated generator unstructured quadrilateral tubes with...
The inclusion of drifts in plasma edge codes like SOLPS-ITER is required to match simulation data with experimental profiles. However, this remains numerically challenging. In paper, the effect some numerical factors on final solution investigated. This study performed three EAST simulations upper single null configuration: an attached purely deuterium case, case limited Ne-seeding, and a detached Ne-seeded case. effects anomalous conductivity thermo-electric coefficient potential are Next,...
Abstract This paper analyzes the neutral fluxes in divertor region of W7-X standard configuration for different input powers, both under attached and detached conditions. The performed analysis is conducted through EMC3-EIRENE simulations. They show importance horizontal to generate neutrals, resolve plugging region. Simulations cases a decrease number generated neutrals compared simulations, addition higher fraction ion flux arriving on baffles during detachment. As ionization takes place...
Abstract We present a semi-automated algorithm for designing three-dimensional divertor or limiter plates targeting low heat loads. The designs the in two stages: Firstly, parallel flux distribution is caught on vertically-inclined at one several toroidal locations. Secondly, power per unit area reduced by stretching, tilting and bending toroidally. Heat transport modeled using EMC3-Lite code, which uses an anisotropic diffusion model.
We apply this scheme to HSX, medium-sized...
Abstract Plasma edge simulations with codes like SOLPS-ITER are widely employed to interpret fusion experiments. However, numerical errors appearing in such rarely investigated, despite their potential large impact on simulation results. These consist of the statistical error and bias, both resulting from finite number EIRENE Monte Carlo particles incomplete convergence, discretization due resolution computational grids. In this contribution, pure deuterium neon seeded H-mode EAST discharges...
The design of divertor targets and baffles for optimal heat particle exhaust from magnetically confined fusion plasmas requires a combination fast, low-fidelity models (such as EMC3-lite [1]) scoping studies high-fidelity ones EMC3-EIRENE [2]) verification. Both those approaches benefit magnetic flux tube mesh fast interpolation mapping field line segments [3]. A new generator unstructured quadrilateral tubes with adaptive refinement is presented integrated into FLARE [4]. For HSX an...
Resilient divertor features connected to open chaotic edge structures in the Helically Symmetric Experiment (HSX) are investigated. For first time, an expanded vessel wall was considered that would give space for implementation of a physical target structure. The analysis done four different magnetic configurations with very plasma edges. A resilient interaction pattern identified across all configurations. This manifests as qualitatively similar footprint behavior equilibria. Overall, field...
Energy dissipation in the plasma edge is key for future tokamaks. The potential of neon as radiating seeding species disconnected double null (DDN) configuration assessed EAST discharges high confinement mode (H-mode). As separation between two separatrices studied DDN minimum 1.5 cm, effectively a single configuration, and benefits topology are minimal. Neon seeding, on other hand, has favourable effect: both target heat flux divertor temperature decrease more than five-fold with increased...
The inclusion of drifts in plasma edge codes like SOLPS-ITER is required to match simulation data with experimental profiles. However, this remains numerically challenging. In paper, the effect some numerical factors on final solution investigated. This study performed three EAST simulations upper single null configuration: an attached purely deuterium case, case limited Ne-seeding and a detached Ne-seeded case. effects anomalous conductivity thermo-electric coefficient potential are Next,...