A5018798477- Magnetic confinement fusion research
- Fusion materials and technologies
- Laser-induced spectroscopy and plasma
- Ionosphere and magnetosphere dynamics
- Atomic and Molecular Physics
- Laser-Plasma Interactions and Diagnostics
- Solar and Space Plasma Dynamics
- Plasma Diagnostics and Applications
- Superconducting Materials and Applications
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Fluid Dynamics and Turbulent Flows
- Dust and Plasma Wave Phenomena
- Particle accelerators and beam dynamics
- Mass Spectrometry Techniques and Applications
- High-Energy Particle Collisions Research
- Gas Dynamics and Kinetic Theory
- Astrophysics and Star Formation Studies
- Metal and Thin Film Mechanics
- Nuclear Physics and Applications
- Stellar, planetary, and galactic studies
- Astro and Planetary Science
- Geomagnetism and Paleomagnetism Studies
- Cold Fusion and Nuclear Reactions
- Meteorological Phenomena and Simulations
Aix-Marseille Université
2016-2025
Physique des interactions ioniques et moléculaires
2015-2024
Centre National de la Recherche Scientifique
2015-2024
Royal Military Academy
2020
CEA Cadarache
2009-2017
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2009-2017
University of California, San Diego
2011
Forschungszentrum Jülich
2010
Japan Atomic Energy Agency
2008
Institute for Atomic and Molecular Physics
2008
In the perspective of operating tungsten monoblocks in WEST, ongoing major upgrade Tore Supra tokamak, a dedicated modelling effort has been carried out to simulate interaction between edge plasma and wall. A new transport code, SolEdge2D–EIRENE, developed with ability up first This is especially important for steady state operation, where thermal loads on all facing components, even remote from plasma, are interest. Moreover, main chamber sources thought dominate contamination core. We...
With WEST (Tungsten Environment in Steady State Tokamak) (Bucalossi et al 2014 Fusion Eng. Des. 89 907–12), the Tore Supra facility and team expertise (Dumont Plasma Phys. Control. 56 075020) is used to pave way towards ITER divertor procurement operation. It consists implementing a configuration installing ITER-like actively cooled tungsten monoblocks tokamak, taking full benefit of its unique long-pulse capability. user platform, open all partners. This paper describes physics basis WEST:...
Abstract Experimental results from several tokamaks suggest a strong impact of divertor density regimes on turbulent transport in the edge plasma. Reciprocally, change transverse and SOL width affects access to regimes, making it fundamental topic for heat exhaust issue. Such phenomenology is highly nonlinear can only be approached quantitatively using numerical simulations treating turbulence neutrals recycling physics self‐consistently. In this study, SOLEDGE3X multi‐fluid code used...
This contribution presents the recent effort at CEA and French federation for fusion to simulate edge plasma transport with new code SOLEDGE3X. The latter can be used both as a 2D or 3D turbulence code. It makes possible simulating up first wall including complex geometry. also includes neutral recycling impurity sputtering, seeding transport. In order improve description in simulation, reduced model intensity prediction has been derived implemented, based on 'k-epsilon' like models from...
Fuel retention, a crucial issue for next step devices, is assessed in present-day tokamaks using two methods: particle balance performed during shots and post-mortem analysis carried out shutdowns between experimental campaigns. Post-mortem generally gives lower estimates of fuel retention than integrated balance. In order to understand the discrepancy these methods, dedicated campaign has been Tore Supra load vessel walls with deuterium (D) monitor trapped D inventory through The was...
Stark broadening of hydrogen lines in the presence a magnetic field is revisited, with emphasis on role ion component under typical conditions magnetized fusion devices. An impact theory for ions valid at low density $({N}_{e}\ensuremath{\lesssim}{10}^{14}\text{ }{\text{cm}}^{\ensuremath{-}3})$ and taking into account Zeeman degeneracy removal atomic states developed. It shown that widths Lorentz triplet components strongly depend field. The model validated by computer simulation method. For...
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 effect of turbulence on the transport neutral species (atom, molecules) in plasmas is investigated. A stochastic model relying a multivariate gamma distribution introduced to describe turbulent fluctuations, and implemented EIRENE. effects fluctuations density ionization source radial profiles are role temperature discussed detail. Calculations with ITER scrape-off layer parameters presented, two distinct regimes respect identified, depending far SOL mean temperature. Finally, influence...
In order to improve cross-field transport description, drifts and currents have been implemented in SOLEDGE2D–EIRENE. The derivation of an equation for the electric potential is recalled. resolution current tested a simple slab case. WEST divertor simulations forward-B reverse-B fields are also discussed. A significant increase ExB shear observed configuration that could explain favorable L-H transition this
A 3D multispecies fluid model has been implemented in the SOLEDGE-TOKAM suite of codes to address Scrape-off layer turbulent impurity transport. Zhdanov closure is used multi-component plasma modeling without any mass ordering or trace assumption. Thanks immersed boundary conditions, up wall simulations with non-axisymmetric facing components are performed, particular WEST configuration. first proof principle interchange turbulence simulation a Deuterium+Carbon also reported.
The WEST experiment is currently operating with tungsten plasma-facing components and testing ITER-like divertor monoblocks. In order to support experiments interpretation, numerical analyses were carried out. Starting from experimental data, realistic background plasma conditions reproduced through SolEdge-EIRENE used as input for ERO2.0 simulations investigate migration. Tungsten contamination due the different was modelled under conditions, highlighting a non-negligible contribution of...
The first simulations of tungsten migration in WEST are performed with the SolEdge2D-EIRENE and ERO2.0 codes to support experimental investigations into erosion plasma-facing components plasma impurity content. impact varying background density on (i) amount penetrating confined plasma, (ii) promptly redeposited fraction, (iii) deposition patterns wall, is investigated under working assumptions a simplified toroidally symmetric wall contour, typical L-mode values transport coefficients,...
Abstract A first set of divertor gas baffles has recently been installed in the TCV tokamak. In order to explore physics determining benefits and limitations baffling guide design a possible second generation baffles, effect baffle closure is investigated using 2D transport code SolEdge2D-EIRENE with realistic wall geometries. The extension scanned, imposing same upstream conditions as previous SOLPS-ITER studies, then extending parameter space access detached plasma conditions. attached...
Abstract Understanding impurity transport in tokamak plasmas is crucial to control radiative losses and material migration future magnetic fusion reactors. In this work we deploy the SolEdge2D-EIRENE code model boundary plasma a WEST discharge, satisfactorily reproducing measurements of both upstream divertor conditions. The spatial distribution oxygen, studied here as representative light impurity, compared vacuum ultraviolet spectroscopy acquired with an oscillating line sight. simulation...
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Abstract To support ITER divertor design, the WEST project on Tore Supra aims at studying high heat fluxes tungsten monoblock during long pulses. In that persective, a particular attention is paid to simulate edge plasma interaction with complex PFCs using transport code SOLEDGE2D‐EIRENE. The response heating and puffing scenario described as well so‐called density regimes, characterizing operational domain of divertor. These results are compared for two different magnetic configurations:...
Plasma material interactions on the first wall of future tokamaks such as ITER and DEMO are likely to play an important role, because turbulent radial transport. The latter results a large extent from propagation plasma filaments through tenuous background. In situation, mean field descriptions (on which transport codes rely) become questionable. First sputtering is particular interest, especially in full W machine, since it has been shown experimentally that sources control core...