A5052083302- Fusion materials and technologies
- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Superconducting Materials and Applications
- Welding Techniques and Residual Stresses
- Non-Destructive Testing Techniques
- Microstructure and Mechanical Properties of Steels
- Metal Alloys Wear and Properties
- Advanced Welding Techniques Analysis
- High-Velocity Impact and Material Behavior
- Fatigue and fracture mechanics
- Magnetic confinement fusion research
- Nuclear and radioactivity studies
- Powder Metallurgy Techniques and Materials
- Metal and Thin Film Mechanics
- Advanced materials and composites
- Hydrogen embrittlement and corrosion behaviors in metals
- Metallurgy and Material Forming
- High Temperature Alloys and Creep
- Engineering Structural Analysis Methods
- Metal Forming Simulation Techniques
- Nuclear Physics and Applications
- Graphite, nuclear technology, radiation studies
- Mechanical Failure Analysis and Simulation
- Aluminum Alloys Composites Properties
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2011-2022
CEA Paris-Saclay
2011-2022
Université Paris-Saclay
2016-2022
Culham Science Centre
2022
Architecture, Territoire, Environnement
2020
American Society of Safety Professionals
2020
Direction des énergies
2008-2017
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...
The scope of the EUFOfusion Work Package Breeding Blanket is to develop a blanket concept for EU DEMO reactor; this includes segments inside Vacuum Vessel and related Tritium Extraction/Removal Systems. In Pre-Concept Design (PCD) Phase, two concepts have been selected as candidates; solid liquid breeder cooled with helium water, respectively. design these systems has adapted plant developed in PCD Phase performances assessed. A large R&D programme implemented evaluate different technologies...
The helium cooled lithium lead (HCLL) blanket concept was originally developed in CEA at the beginning of 2000: it is one two European concepts to be tested ITER form a test module (TBM) and four currently being considered for DEMOnstration reactor that will follow ITER. TBM highly optimized component environment provide crucial information development DEMO blanket, but its design needs adapted reactor. With respect design, reduction steel content breeding zone (BZ) sought order maximize...
One of the main nuclear materials is austenitic stainless steels, which have good ductility and toughness, high thermal expansion coefficients a conductivity lower than that martensitic or ferritic steels. The 316L(N) steel (X2CrNiMo17-12-2 with controlled nitrogen) evaluated for structures such as vessels, are enclosures surrounding reactor core its assemblies, in fourth generation systems. RCC-MR code, used frame reference manufacture SFR (Sodium Fast Reactor concept), recommends use...