A5088172720- Magnetic confinement fusion research
- Fusion materials and technologies
- Nuclear reactor physics and engineering
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Laser-Plasma Interactions and Diagnostics
- Advanced Machining and Optimization Techniques
- Fluid Dynamics and Turbulent Flows
- Gas Dynamics and Kinetic Theory
- Ionosphere and magnetosphere dynamics
- Manufacturing Process and Optimization
- Computational Fluid Dynamics and Aerodynamics
- Advanced Surface Polishing Techniques
- Advanced machining processes and optimization
- Topology Optimization in Engineering
- Plasma Diagnostics and Applications
- Heat Transfer and Optimization
- Advanced Data Storage Technologies
- Advancements in Photolithography Techniques
- Non-Destructive Testing Techniques
- Welding Techniques and Residual Stresses
- Solar and Space Plasma Dynamics
- Electron and X-Ray Spectroscopy Techniques
- Geomechanics and Mining Engineering
- Modeling, Simulation, and Optimization
KU Leuven
2016-2025
ITER
2016-2017
Forschungszentrum Jülich
2014-2017
Belgian Nuclear Research Centre
1959
We present in this paper the code package SOLPS-ITER, initially introduced by S. Wiesen et al. [J. Nucl. Mater. 463, 480 (2015)], dedicated to simulations of plasmas edge region fusion devices. This brings together previously existing SOLPS implementations and aims become new standard version. summarize benchmarking work done ensure backward compatibility with previous work, a strong requirement on maintaining viability usability already extensive database runs used for ITER divertor design...
Abstract The tokamak à configuration variable (TCV) continues to leverage its unique shaping capabilities, flexible heating systems and modern control system address critical issues in preparation for ITER a fusion power plant. For the 2019–20 campaign configurational flexibility has been enhanced with installation of removable divertor gas baffles, diagnostic capabilities an extensive set upgrades new dual frequency gyrotrons. baffles reduce coupling between main chamber allow detailed...
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....
In plasma edge simulations using the SOLPS-ITER code, simulated Scrape-Off Layer domain has historically been restricted to magnetic flux surfaces contacting divertor targets at both ends.We present here a newly developed numerical solver for B2.5 in SOLPS-ITER, allowing grid be extended true vessel boundaries.The new, unstructured Finite Volume scheme can deal with arbitrary grids and topologies 2D poloidal plane.It includes correct treatment of possibly misaligned faces cells w.r.t. field...
Abstract Neutral gas physics and neutral interactions with the plasma are key aspects of edge divertor in a fusion reactor including detachment phenomenon often seen as to dealing power exhaust challenges. A full description dynamics requires 6D kinetic approach, potentially time dependent, where details wall geometry play substantial role, extent that, e.g., subdivertor region has be included. The Monte Carlo (MC) approach used for about 30 years EIRENE (Reiter et al 2005 Fusion Sci....
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 The neutral atoms in the plasma edge of nuclear fusion devices are typically modeled using either a fluid or kinetic approach. approach is most accurate, but it has two main disadvantages. First, usual solution high-dimensional equation Monte Carlo techniques introduces statistical noise, which hampers convergence coupled plasma-neutral model. Second, computational time strongly increases for highly collisional regimes. For these reasons, deterministic models remain an attractive...
As part of an effort to validate the edge plasma model in SOLPS-ITER code suite under ITER-relevant divertor and neutral conditions, we report on progress modeling Alcator C-Mod with new code. We perform simulations a complete drifts kinetic neutrals, including effects viscosity, ion-molecule collisions Lyα-opaque but assuming pure deuterium plasma. Through series varying geometries, show importance neutal leakage paths through substructure solution. Moreover, impact inner-outer target...
Tokamak divertor design for next-step fusion reactors heavily relies on numerical simulations of the plasma edge. Currently, process is mainly done in a forward approach, where designer strongly guided by his experience and physical intuition proposing shapes, which are then thoroughly assessed computations. On other hand, automated methods based optimization have proven very successful related field aerodynamic design. By recasting objectives constraints into framework mathematical problem,...
SOLPS-ITER is a new edge code package that will be developed and maintained at the ITER Organization [X. Bonnin et al., Plasma Fusion Res. 11, 1403102 (2016)], in close collaboration with wider SOLPS community, used to support design of divertor [A.S. Kukushkin Eng. Des. 86, 2865 (2011)]. In this paper, we report on first application modeling Alcator C-Mod divertor. With its high density, magnetic field, strong ITER-like target shaping, particular interest terms plasma neutral parameters We...
First of a kind SOLPS-ITER simulations on tokamak á configuration variable (TCV) that include nitrogen have been performed to model recent seeded detachment experiments. Based spectroscopic measurements, recycling coefficient 0.3–0.5 the graphite walls TCV is estimated. The experimentally observed decrease core density with increasing plasma reproduced and linked reduction ionisation mean free path in scrape-off layer. Although influence sputtered carbon impurities from TCV's wall cannot be...
Quantifying main chamber wall recycling, erosion and resulting material migration, at least on the basis of known or empirical far scrape-off layer (SOL) processes, is still highly uncertain, despite its relevance for ITER fusion reactor design studies. This affects, example, problem first mirror performance many optical diagnostics in harsh environment. Poor computational access not due to a fundamental technical limitation apparently all current tokamak edge plasma fluid codes, which...
This paper examines the effect of grid resolution on solution a B2-EIRENE simulation partially detached ITER divertor plasma. Due to large amount required computational time in coupled finite-volume/Monte-Carlo codes, simulations plasma edge are typically run coarse grids. However, new averaging techniques make with finer grids feasible. Starting from original numerical grid, performed two successively Results error analysis reveal that discretization errors large. Peak values particularly...
The SOLPS-ITER code suite is used worldwide for plasma edge modeling, the interpretation of experiments, as well design ITER divertor. numerical scheme solver code, B2.5, based on assumption perfectly orthogonal grids in poloidal plane, aligned with magnetic field, while practice are often strongly distorted to match divertor target shapes. Neglecting these grid distortion leads qualitatively and quantitatively incorrect results fluid neutral simulations, may affect cold (detached) divertors...
Abstract Only recently, plasma edge simulations up to the wall have been enabled with SOLPS‐ITER. This requires dedicated gridding techniques reconcile grid alignment magnetic field and refinement toward as quality is primordial ensure fast reliable convergence. Therefore, approach for grids analyzed improved. A truncation error analysis performed on discrete operators of discretization scheme in SOLPS‐ITER, resulting indicators properties that are undesired. Based these indicators,...
We derive fluid neutral approximations for a simplified 1D edge plasma model, suitable to study the behavior close target of nuclear fusion divertor, and compare its solutions solution corresponding kinetic Boltzmann equation. The is considered as fixed background extracted from detached 2D simulation. show that Maxwellian equilibrium distribution already obtained very target, justifying use approximation. three models: (i) diffusion model; (ii) pressure-diffusion model (i.e., combination...