A5060403346- Fusion materials and technologies
- Magnetic confinement fusion research
- Nuclear Materials and Properties
- Laser-induced spectroscopy and plasma
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Ion-surface interactions and analysis
- Superconducting Materials and Applications
- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Metal and Thin Film Mechanics
- Diamond and Carbon-based Materials Research
- Particle accelerators and beam dynamics
- Atomic and Molecular Physics
- Analytical chemistry methods development
- Dust and Plasma Wave Phenomena
- Advanced Materials Characterization Techniques
- Nuclear materials and radiation effects
- Radioactive contamination and transfer
- Ionosphere and magnetosphere dynamics
- Advanced materials and composites
- Nuclear and radioactivity studies
- High-pressure geophysics and materials
- Radioactive element chemistry and processing
- Laser Material Processing Techniques
Institut de Recherche sur la Fusion par Confinement Magnétique
2015-2024
CEA Cadarache
2015-2024
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2015-2024
Institut de Biosciences et Biotechnologies
2024
Aix-Marseille Université
2009-2024
Centre National de la Recherche Scientifique
1985-2024
Australian National University
2019-2020
CEA Grenoble
2020
Royal Military Academy
2020
Moscow Engineering Physics Institute
2014-2019
The major increase in discharge duration and plasma energy a next step DT fusion reactor will give rise to important plasma-material effects that critically influence its operation, safety performance. Erosion scale of several centimetres from being barely measurable at micron today's tokamaks. Tritium co-deposited with carbon strongly affect the operation machines facing components. Controlling plasma-wall interactions is critical achieving high performance present day tokamaks, this likely...
The provision of a particle and power exhaust solution which is compatible with first-wall components edge-plasma conditions key area present-day fusion research mandatory for successful operation ITER DEMO. work package plasma-facing (WP PFC) within the European programme complements laboratory experiments, i.e. in linear plasma devices, electron ion beam loading facilities, studies performed toroidally confined magnetic such as JET, ASDEX Upgrade, WEST etc. connection both groups done via...
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 As part of the development proven diagnostics allowing characterization ITER’s PFUs (Plasma Facing Units) without dismantling, LIBS (Laser-Induced Breakdown Spectroscopy) is a serious candidate for determining multi-elemental composition. In this article, we report measurement campaign carried out within WEST tokamak using an original device based on following technological choices. (1) The laser source and spectrometer are placed outside tokamak. (2) pulses conveyed by optical...
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...
Upgrade of the Tore Supra ergodic divertor (ED) has led to significant progress in ED physics. Pulse durations 30?s with LHCD have been achieved demonstrating heat exhaust capability both actively cooled technology at hand and this specific concept. The disruptive limit governed by stochastization outer magnetic surfaces is found occur for a value Chirikov parameter reaching two on surface q = 2+(3/12). This experimentally observed robustness allows one operate very low safety factor...
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...
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 Surface and near-surface morphology evolution of helium-irradiated tungsten due to thermal cycling up the ITER-relevant temperature 1350 K was studied using electron microscopy positron annihilation spectroscopy techniques. Holes at surface bubbles in recrystallized polycrystalline samples were created by 75 eV helium plasma irradiation with fluence 3 × 10 23 He m −2 1073 K. Subsequent annealing experiments combined a detailed analysis investigate shape density changes holes respect...
Two populations of dust particles were found during the first phase operation WEST. The one that dominates by size and weight comes from delamination tungsten coatings covering graphite tiles emission droplets molten materials off-normal events. Sizes vary several microns to tens microns. More generally, micron-sized due erosion all present in vacuum vessel collected. In addition, nanocavities at surface sampled after He plasmas attributed trapping form nanobubbles. Tungsten nanoparticles...
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...
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....