A5067726239- Fusion materials and technologies
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Superconducting Materials and Applications
- Hydrogen Storage and Materials
- Ion-surface interactions and analysis
- Advanced Materials Characterization Techniques
- Metal and Thin Film Mechanics
- Advanced Chemical Physics Studies
- Laser-Plasma Interactions and Diagnostics
- nanoparticles nucleation surface interactions
- Cold Fusion and Nuclear Reactions
- Nuclear materials and radiation effects
- Atomic and Molecular Physics
- Diamond and Carbon-based Materials Research
- Particle accelerators and beam dynamics
- Thermal properties of materials
- Fuel Cells and Related Materials
- Plasma Diagnostics and Applications
- Hydrogen embrittlement and corrosion behaviors in metals
- Muon and positron interactions and applications
- High-Temperature Coating Behaviors
- Dust and Plasma Wave Phenomena
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2016-2025
CEA Cadarache
2016-2025
Institut de Recherche sur la Fusion par Confinement Magnétique
2015-2024
Physique des interactions ioniques et moléculaires
2018-2021
University of Helsinki
2018-2020
Royal Military Academy
2020
Helsinki Institute of Physics
2019
Aix-Marseille Université
2017-2018
Centre National de la Recherche Scientifique
2017-2018
Helsinki Art Museum
2018
FESTIM (Finite Element Simulation of Tritium In Materials), is a versatile open-source finite element code developed in Python for simulating hydrogen transport materials. addresses limitations observed existing codes by enabling multi-dimensional, multi-material simulations, leveraging the flexible method and FEniCS library. Use cases illustrating FESTIM's applicability efficacy are presented: reproduction thermo-desorption experiments, modelling plasma-facing components (divertor...
The new full-metal ITER-like wall (ILW) at JET was found to have a profound impact on the physics of disruptions. main difference is significantly lower fraction (by up factor 5) energy radiated during disruption process, yielding higher plasma temperatures after thermal quench and thus longer current times. Thus, larger total conducted resulting in heat loads. Active mitigation by means massive gas injection became necessity avoid beryllium melting already moderate levels magnetic (i.e....
Evaluating the mole fraction of hydrogen isotopes in a solid is difficult task. Few methods allow it to be achieved. LIBS laser method based on electronic excitation elements and spontaneous emission characteristic optical lines. On sample containing isotopes, α-type lines can estimate their total fraction. In addition, discriminating because separate contributions isotopes. This paper reports implementation this thin film-type samples tritium. They consist nanometric layers palladium...
Simulations of deuterium (D) atom exposure in self-damaged polycrystalline tungsten at 500 K and 600 are performed using an evolution the MHIMS (migration hydrogen isotopes materials) code which a model to describe interaction D with surface is implemented. The surface-energy barriers for both temperatures determined analytically steady-state analysis. desorption energy per from 0.69 ± 0.02 eV 0.87 0.03 K. These values good agreement ab initio calculations as well experimental determination...
Density Functional Theory studies show that in tungsten a mono vacancy can contain up to 6 Hydrogen Isotopes (HIs) at 300K with detrapping energies varying the number of HIs vacancy.Using these predictions, multi trapping rate equation model has been built and used thermal desorption spectrometry (TDS) experiments performed on single crystal after deuterium ions implantation.Detrapping obtained from adjust temperature TDS spectrum observed experimentally are good agreement DFT values within...
Fusion fuel retention (trapping) and release (desorption) from plasma-facing components are critical issues for ITER any future industrial demonstration reactors such as DEMO. Therefore, understanding the fundamental mechanisms behind of hydrogen isotopes in first wall divertor materials is necessary. We developed an approach that couples dedicated experimental studies with modelling at all relevant scales, microscopic elementary steps to macroscopic observables, order build a reliable...
Abstract In this work we investigated the adsorption of oxygen and co-adsorption hydrogen on (110) surface tungsten by means Density Functional calculations. The absorption, recombination release mechanisms across with are further established at saturation above surface. It is found that both adsorb preferentially three-fold sites. limit was determined to one monolayer in adsorbate. Oxygen lower binding energy activation barrier for molecular hydrogen. Finally, as clean surface,...
Abstract A damage-induced hydrogen trap creation model is proposed, and parameters for tungsten are identified using experimental data. The methodology obtaining these thermo-desorption analysis spectra data outlined. Self-damaged optionally annealed samples have undergone TDS analysis, which has been analysed to identify the properties of extrinsic traps induced by damage determine how they evolve with annealing temperature. parametric study investigated impact rate temperature on tritium...
Recent studies dedicated to the characterisation of in-vessel dust in JET with new ITER-like wall (ILW) show that levels are orders magnitude lower compared latter stages carbon-wall (CW) period and decreasing operational time. Less than 1 g was recovered a recent inspection, more 200 material at end JET-CW life. inspection ILW shows low rates re-deposition only small areas damage type likely create particulate matter. Quantifiers from laser scattering techniques also indicate an order...
Deuterium retention was for the first time measured in tungsten samples simultaneously irradiated by W ions and exposed to D atoms at five different temperatures from 450 K 1000 K. In order obtain information on defect concentration, were afterwards 600 populate created defects. The results compared sequential damaging/exposure experiments. Synergistic effects observed, namely, higher concentrations found case of simultaneous damaging D-atom loading as elevated populating defects afterwards....
The behaviour of hydrogen isotopes in ITER monoblocks was studied using the code FESTIM (Finite Element Simulation Tritium In Materials) which is introduced this publication. has been validated by reproducing experimental data and Method Manufactured Solutions used for analytical verification. Following relevant plasma scenarios, both transient heat transfer (HIs) diffusion have simulated order to assess HIs retention monoblocks. Relevant materials properties used. Each cycle composed a...
Herein we investigate absorption and desorption of hydrogen in the sub-surface tungsten via density functional theory. Both near-surface diffusion recombination a bulk atom with adsorbed upon W(1 1 0) 0 surfaces are investigated at various surface adsorption coverage ratios. This study intends to model processes occurring during thermal-desorption spectroscopy experiments gaseous or low energy atomic exposure. Since expected change as varies, different ratios were on both surfaces. We found...
The effect of deuterium (D) presence on the amount displacement damage created in tungsten (W) during high-energy W-ion irradiation is investigated. For this purpose, we have performed modelling experimental results where W was sequentially or simultaneously irradiated by 10.8 MeV ions and exposed to 300 eV D ions. A novel creation stabilization model newly developed introduced into MHIMS-Reservoir (migration hydrogen isotopes materials) code. It employs macroscopic rate equations (MREs) for...
In this work, the deuterium (D) retention in plasma facing components of divertor ITER is estimated. Three scenarios are simulated with 3 different surface temperatures, 1456 K, 870 K and 435 K. They represent exposure parts during an attached plasma. Our 1D rate equation code MHIMS (migration hydrogen materials) used to model super-saturated layer formed first 10 nm: D integrated nm-layer ≈1019 m−2 for coldest scenarios. It also differentiate evolution pulsed continuous exposures which...
In this paper, we combine density functional theory data with a thermodynamic and kinetic model to determine the total concentration of hydrogen implanted in subsurface tungsten exposed flux. The is calculated given flux hydrogen, temperature implantation, energy incoming ions as independent variables. This global built step by step; an equilibrium between atomic within bulk molecular gas phase first considered, solubility compared experimental results. Subsequently, used chemical potential...
ou non, émanant des établissements d'enseignement et de recherche français étrangers, laboratoires publics privés.
Plasma-facing materials for next generation fusion devices, like ITER and DEMO, will be submitted to intense fluxes of light elements, notably He H isotopes (HI). Our study focuses on tritium (T) retention a wide range W samples: first, different types were investigated distinguish the impact pristine original structure retention, from W-coated samples ITER-grade pure various annealing manufacturing procedures, along with monocrystalline reference. Then, He-D irradiated studied investigate...
The impact of helium (He) plasma exposure with He fluxes relevant for ITER and WEST on the near-surface microstructure polycrystalline tungsten (W) is investigated by coupling transmission electron microscopy (TEM) analysis thermal desorption spectrometry (TDS) measurements. samples were exposed in PSI-2 linear device to 75 eV ions up fluence 3 × 1023 m−2 surface temperature range 1053–1073 K. obtained bubbles–enriched W are subsequently probed sequences low flux 250 deuterium (D) ion...
Abstract Rate equation modelling is performed to simulate <?CDATA ${\mathrm{D_2}}$?> <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msub> <mml:mi mathvariant="normal">D</mml:mi> <mml:mn>2</mml:mn> </mml:msub> </mml:mrow> </mml:math> and ${\mathrm{D_2}}+{\mathrm{D}_2^+}$?> <mml:mo>+</mml:mo> <mml:msubsup> </mml:msubsup> exposure of the ${\mathrm{W}(110)}$?> mathvariant="normal">W</mml:mi> <mml:mo stretchy="false">(</mml:mo> <mml:mn>110</mml:mn>...
Based on macroscopic rate equation simulations of tritium migration in an actively cooled tungsten (W) plasma facing component (PFC) using the code MHIMS (migration hydrogen isotopes metals), estimation has been made retention ITER W divertor target during a non-uniform exponential distribution particle fluxes. Two grades materials are considered to be exposed ions: undamaged and damaged fast fusion neutrons. Due strong temperature gradient PFC, Soret effect's impacts is also evaluated for...