A5046461286- Magnetic confinement fusion research
- Fusion materials and technologies
- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Nuclear Physics and Applications
- Ionosphere and magnetosphere dynamics
- Metal and Thin Film Mechanics
- Metallurgical Processes and Thermodynamics
- Ion-surface interactions and analysis
- Atomic and Molecular Physics
- Solar and Space Plasma Dynamics
- Laser-induced spectroscopy and plasma
- Particle accelerators and beam dynamics
- Advanced Data Storage Technologies
- High-Energy Particle Collisions Research
- Catalytic Processes in Materials Science
- Stochastic processes and financial applications
- Hydrogen embrittlement and corrosion behaviors in metals
- High-Temperature Coating Behaviors
- Radiation Effects in Electronics
- Graphite, nuclear technology, radiation studies
- Non-Destructive Testing Techniques
Forschungszentrum Jülich
2016-2024
CEA Cadarache
2024
Atlas Copco (Germany)
2022
Ernst Ruska Centre
2021
Royal Military Academy
2020
ITER will use beryllium as a plasma-facing material in the main chamber, covering total surface area of about 620 m2. Given importance erosion and co-deposition for tritium retention ITER, significant efforts have been made to understand behaviour under fusion-relevant conditions with high particle heat loads. This paper provides comprehensive report on state knowledge conditions: mechanisms their consequences, migration JET, fuel dust generation. The reviews basic laboratory studies,...
Abstract After the second Deuterium–Tritium Campaign (DTE2) in JET tokamak with ITER-Like Wall (ILW) and full tritium campaigns that preceded followed after DTE2, a sequence of fuel recovery methods was applied to promote removal from wall components. The started several days baking main chamber walls at 240 °C 320 °C. Subsequently, superimposed Ion-Cyclotron Conditioning (ICWC) Glow Discharge (GDC) cleaning cycles deuterium. Diverted plasma operation deuterium different strike point...
Abstract This work investigates the role of surface topography in sputtering process tungsten (W) exposed to helium plasma using GyM linear device. Surfaces with varying roughness, from sub-nanometer ≅1 μm, and different textures, including random-like regular configurations, were studied. The samples at energies 30 350 eV, fluence ≅4.3e24 He + m -2 temperatures well below bulk W fuzz formation threshold ≅700 °C. interpretation experimental results was supported by simulations ERO2.0 code....
The Wendelstein 7-X (W7-X) optimized stellarator fusion experiment, which went into operation in 2015, has been operating since 2017 with an un-cooled modular graphite divertor. This allowed first divertor physics studies to be performed at pulse energies up 80 MJ, as opposed 4 MJ the phase, where five inboard limiters were installed instead of a This, and number other upgrades device capabilities, extension regimes higher plasma density, heating power, performance overall, e.g. setting new...
The recently developed Monte-Carlo code ERO2.0 is applied to the modelling of limited and diverted discharges at JET with ITER-like wall (ILW). global beryllium (Be) erosion deposition simulated compared experimental results from passive spectroscopy. For limiter configuration, it demonstrated that Be self-sputtering an important contributor (at least 35%) erosion. Taking this contribution into account, confirms previous evidence high deuterium (D) surface concentrations up ∼ 50% atomic...
Abstract The paper provides an overview of recent modelling global material erosion and deposition in the fusion devices Wendelstein 7-X (W7-X), JET ITER using Monte-Carlo code ERO2.0. For validating tool a three-dimensional environment, W7-X simulations are performed to describe carbon from graphite test divertor units, which were equipped operational phase OP 1.2 analysed post-mortem. Synthetic spectroscopy line emission is compared with experimental results spectrometer measurement...
Abstract Deuterium (D) and beryllium (Be) fluxes are obtained in JET Low-confinement (L-mode) plasmas at the outer limiters of first wall using calibrated visible cameras. They inferred from measured radiances spectroscopic S/XB method. From fluxes, effective gross erosion yield Yeff limiter surface is estimated. After discussing uncertainties proposed methodology, we show dependence deduced particle recent L-mode on: separatrix-limiter clearance, magnetic field plasma current, NBI ICR...
ERO is a Monte-Carlo code for modeling plasma-wall interaction and 3D plasma impurity transport applications in fusion research. The has undergone significant upgrade (ERO2.0) which allows increasing the simulation volume order to cover entire edge of device, allowing more self-consistent treatment comparison with larger number variety experimental diagnostics. In this contribution, physics-relevant technical innovations new version are described discussed. capabilities demonstrated by...
Main processes of plasma-wall interaction and impurity transport in fusion devices their impact on the availability are presented modelling tools, particular three-dimensional Monte-Carlo code ERO, introduced. The capability ERO is demonstrated example tungsten erosion deposition modelling. dependence plasma temperature density studied by simulations with a simplified geometry assuming (almost) constant parameters. amount increases increasing electron density. Up to 100% eroded can be...
The erosion, transport and deposition of tungsten in the outer divertor JET-ILW has been studied for an H-Mode discharge with low frequency ELMs. For this specific case inter-ELM electron temperature at strike point about 20 eV, sputtering between ELMs is almost exclusively due to beryllium impurity self-sputtering. However, during deuterium becomes important even dominates. amount simulated local relative sputtered very high reaches values 99% density 5E13 cm−3 temperatures 10 30 eV....
Abstract The Monte-Carlo code ERO2.0 was used to simulate steady-state erosion and transport of beryllium (Be) in the ITER main chamber. Various plasma scenarios were tested, including a variation species (hydrogen, deuterium, helium), conditions (density, temperature, flow velocity) magnetic configurations. study provides valuable predictions for Be divertor, where it is expected be an important contributor dust formation fuel retention due build-up co-deposited layers. gross net rates...
• Experiments on tungsten (W) erosion and transport in Argon (Ar) plasma were conducted at the linear device PSI-2. W was measured with three methods: WI spectroscopy, mass loss quartz micro-balance (QMB) deposition sensor. PSI-2 experiments modelled 3D Monte-Carlo code ERO, which have reproduced well all main trends observed. In general, our resulting sputtering yields are consistent SDTrimSP simulations within 50%. Series of independent WΙ Consistent set data produced these interpreted...
Surface morphology and its evolution during the plasma irradiation is known to have a large influence on erosion resulting lifetime of plasma-facing components as well tritium retention. For instance, surface roughness can affect physical sputtering, re-deposition, angular distributions sputtered species. In this study effect implemented into 3D Monte-Carlo code ERO2.0. First modelling results for molybdenum (Mo) irradiated with deuterium (D) in conditions foreseen planned experiments at...
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...
Abstract W7-X completed its plasma operation in hydrogen with island divertor and inertially cooled test unit (TDU) made of graphite. A substantial set plasma-facing components (PFCs), including particular marker target elements, were extracted from the vessel analysed post-mortem. The analysis provided key information about underlying plasma–surface interactions (PSI) processes, namely erosion, transport, deposition as well fuel retention graphite components. net carbon (C) erosion...
Abstract A sequence of fuel recovery methods was tested in JET, equipped with the ITER-like beryllium main chamber wall and tungsten divertor, to reduce plasma deuterium concentration less than 1% preparation for operation tritium. This also a key activity regard refining clean-up strategy be implemented at end 2nd DT campaign JET (DTE2) assess tools that are envisaged mitigate tritium inventory build-up ITER. The began 4 days baking 320 °C, followed by further which Ion Cyclotron Wall...
Abstract The 3D ERO code, which simulates plasma–wall interaction and impurity transport in magnetically confined fusion‐relevant devices is described. As application, prompt deposition of eroded tungsten has been simulated at surfaces with shallow magnetic field 3 T. Dedicated PIC simulations have performed to calculate the characteristics sheath front plasma–exposed use as input for these simulations. Prompt reaches 100% highest electron temperature density. In comparison more simplified...
Abstract ERO2.0 is a recently developed Monte‐Carlo code for modelling global erosion and redeposition in fusion devices. We report here on the code's application to ITER studying of beryllium (Be) first wall armour under burning plasma steady state diverted conditions. An important goal study provide synthetic signals design two key diagnostics: main chamber visible spectroscopy laser in‐vessel viewing systems. The simulations are performed using toroidally symmetric backgrounds obtained by...
Abstract Predictive edge and core simulations of tungsten (W) erosion transport in JET ITER-like wall plasmas are shown to be consistent with the experimentally inferred W density main plasma, within uncertainty inherited from measurements deuterium plasma conditions measurements. The ERO2.0 code is applied predicting transport, whereas JINTRAC predicts pedestal top plasma. studied scenarios range L-mode highest-performance ELMy H-mode JET.
Abstract The deposition/erosion on optical diagnostic components—mirrors—is a critical issue in reactor class devices with long-pulsed high fluence plasma operation. paper presents results of the three-dimensional Monte–Carlo code ERO2.0 for two aperture and first mirror geometries to be deployed ITER, along separate simulation study that aims replicate from an experimental first-mirror carried out JET. Promisingly, very little impurity deposition mirrors anticipated durations is found...
Physical and chemical assisted physical sputtering were characterised by the Be I II line BeD band emission in observation chord measuring sightline integrated front of inner beryllium limiter at torus midplane. The 3D local transport plasma-surface interaction Monte-Carlo modelling (ERO code [18]) is a key for interpretation observations vicinity shaped solid limiter. plasma parameter variation (density scan) regime has provided useful material simulation benchmark. improved background...
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,...