A5004993804- Fusion materials and technologies
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- Nuclear reactor physics and engineering
- Superconducting Materials and Applications
- Advanced materials and composites
- Nuclear Physics and Applications
- Metal and Thin Film Mechanics
- Metallurgical Processes and Thermodynamics
- Diamond and Carbon-based Materials Research
- Particle accelerators and beam dynamics
- High-Temperature Coating Behaviors
- Laser-induced spectroscopy and plasma
- Advanced Materials Characterization Techniques
- Laser-Plasma Interactions and Diagnostics
- Gas Dynamics and Kinetic Theory
- Ionosphere and magnetosphere dynamics
- Microstructure and mechanical properties
- Electromagnetic Launch and Propulsion Technology
- Plasma Diagnostics and Applications
- High-pressure geophysics and materials
- Laser Material Processing Techniques
- Theoretical and Computational Physics
- Metallurgical and Alloy Processes
- Advanced ceramic materials synthesis
CEA Cadarache
2015-2024
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2015-2024
Institut de Recherche sur la Fusion par Confinement Magnétique
2011-2024
Culham Science Centre
2022
DSM (Netherlands)
2014-2020
National Agency for New Technologies, Energy and Sustainable Economic Development
2015
Centre National de la Recherche Scientifique
2009
Aix-Marseille Université
2009
Physique des interactions ioniques et moléculaires
2007
In a power plant scale fusion reactor, huge amount of thermal produced by the reaction and external heating must be exhausted through narrow area divertor targets. The targets withstand intense bombardment diverted particles where high heat fluxes are generated erosion takes place on surface. A considerable volumetric nuclear also exhausted. To cope with such an unprecedented exhaust challenge, highly efficient cooling capacity is required. Furthermore, fulfill other critical functions as...
Recently, an integrated program of conceptual design activities for the European DEMO reactor was launched in framework EUROfusion Consortium, where reliable power handling capability identified as one most critical scientific well technological challenges a reactor. The divertor is key in-vessel plasma-facing component being charge exhaust and removal impurity particles. target will have to withstand extreme thermal loads local peak heat flux expected reach up 20 MW/m2 during slow transient...
The divertor target plates are the most thermally loaded in-vessel components in a fusion reactor where high heat fluxes produced on plasma-facing (PFCs) by intense plasma bombardment, radiation and nuclear heating. For reliable exhaust of huge thermal power, robust durable PFCs with sufficiently large removal capability lifetime has to be developed. Since 2014 framework preconceptual design activities EUROfusion DEMO project, integrated R&D efforts have been made subproject 'Target...
The first EAST (Experimental Advanced Superconducting Tokamak) plasma ignited in 2006 with non-actively cooled steel plates as the plasma-facing materials and components (PFMCs) which were then upgraded into full graphite tiles bolted onto water-cooled copper heat sinks 2008. wall was changed further molybdenum alloy 2012, while keeping for both upper lower divertors. With rapid increase heating current driving power EAST, W/Cu divertor project launched around end of aiming at achieving...
The EUROfusion materials research program for DEMO in-vessel components aligns with the European Fusion Roadmap and comprises characterization qualification of baseline EUROFER97, CuCrZr tungsten, advanced structural high heat flux developed risk mitigation, as well optical dielectric functional materials. In support future engineering design activities, focus is primarily to assemble qualified data supply process generate material property handbooks, assessment reports, criteria limits...
After three years of operation (2017–2019) and four experimental campaigns (C1 to C4), the first phase WEST tokamak has now come an end. During that period, operated with tungsten coated copper-based carbon-based plasma facing components in order comply a full metallic environment. A set components, called units, using ITER monoblock technology was also installed onto one sector lower divertor test their behaviour real This paper gives overview ageing these during situ visual inspections. It...
Abstract The net erosion and deposition patterns in the inner outer divertor of WEST were determined after different experimental campaigns (C3 C4) first operational phase using ion beam analyses scanning electron microscopy techniques. performed on four entire tiles from inertially cooled, W-coated units with an additional Mo marker coating covered a further W coating. Strong occurred at expected location strike line area campaign-averaged rate >0.1 nm s −1 . On high field side area,...
Abstract The consequences of tungsten (W) melting on divertor lifetime and plasma operation are high priority issues for ITER. Sustained controlled W-melting experiment has been achieved the first time in WEST a poloidal sharp leading edge an actively cooled ITER-like facing unit (PFU). A series dedicated power steady state discharges were performed to reach point tungsten. was exposed parallel heat flux about 100 MW.m −2 up 5 s providing melt phase 2 without noticeable impact (radiated...
Studying the ageing of tungsten monoblocks, their erosion and fuel inventory is priority WEST post-mortem analyses programme. Actively-cooled ITER-like plasma-facing units (PFUs) special W-coated marker lower divertor tiles were retrieved from after C3 C4 experimental campaigns to perform ex-situ analyses. The erosion/deposition pattern on was determined. deposition found mainly inner side which covered by layered deposits that increase in thickness radial direction a few hundreds nm maximum...
In the WEST tokamak, ITER-like divertor targets consisting of tungsten monoblocks bonded via an OHFC-Cu compliance layer to CuCrZr cooling tubes were exposed plasma during 2018 experimental campaign in which modest heating power was available. Up 2.5 MW/m2 surface heat flux attained. Inspection components after revealed a wide variety damage at both leading and trailing monoblock edges, optical hot spots are projections along magnetic field lines toroidal gaps between onto poloidal edges....
Wendelstein 7-X, the world's largest superconducting stellarator in Greifswald (Germany), started plasma experiments with a water-cooled plasma-facing wall 2022, allowing for long pulse operation. In parallel, project was launched 2021 to develop W based divertor, replacing current CFC demonstrate performance of reactor relevant facing materials low tritium retention. The consists two tasks: Based on experience from previous experimental campaigns and improved physics modelling, geometry...