A5055354683- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Fusion materials and technologies
- Nuclear Materials and Properties
- Physics of Superconductivity and Magnetism
- Thermal Analysis in Power Transmission
- Gyrotron and Vacuum Electronics Research
- Spacecraft and Cryogenic Technologies
- Nuclear reactor physics and engineering
- Laser-induced spectroscopy and plasma
- Iterative Learning Control Systems
- High-Temperature Coating Behaviors
- Silicon Carbide Semiconductor Technologies
- Terrorism, Counterterrorism, and Political Violence
- Political Conflict and Governance
- Fault Detection and Control Systems
- Silicon and Solar Cell Technologies
- Nuclear Physics and Applications
- Heat Transfer Mechanisms
- Ionosphere and magnetosphere dynamics
- Advanced materials and composites
- Quality Function Deployment in Product Design
- Advanced Control Systems Optimization
- Health and Conflict Studies
CEA Cadarache
2006-2023
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2007-2023
Nature Inspires Creativity Engineers Lab
2023
Institut de Recherche sur la Fusion par Confinement Magnétique
1993-2016
Shell (United States)
2015
DSM (Netherlands)
2013
Aix-Marseille Université
2009
Centre National de la Recherche Scientifique
2009
Universidad Complutense de Madrid
1993-1995
Rockwell Automation (United States)
1993
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...
The world's largest pulsed superconducting coil was successfully tested by charging up to 13 T and 46 kA with a stored energy of 640 MJ. ITER central solenoid (CS) model CS insert were developed fabricated through an international collaboration, their cooldown tests carried out test operation teams. In tests, where the original goal 0.4 T/s T, achieved ramp rates 0.6 1.2 T/s, respectively. addition, charged discharged 10 003 times in background field no degradation operational temperature...
In the framework of controlled nuclear fusion by magnetic confinement programme, a particular design Cable-in-Conduit Conductor (CICC) is being developed, including two parallel cooling channels. The central channel separated from strand spiral structure whose geometry can substantially influence overall pressure drop. thermo-hydraulics this so called dual CICC not well known. Hence various experiments with pressurised nitrogen at room temperature, on straight and curved unit lengths ITER...
A correlation has been developed for the turbulent friction factor f of a circular channel with helical rib roughness rectangular cross section, which is relevant to central (hole) in two-channel cable-in-conduit conductors. The based on data we measured pipe three different types helix. It relates Reynolds number Re and suitable dimensionless combinations all geometrical parameters problem, i.e., hole diameter helix gap thickness. limited comparison actual (QUELL) conductor shows good agreement.
The Poloidal Field (PF) coils of the International Thermonuclear Experimental Reactor (ITER) are designed with NbTi cable-in-conduit conductors wound in double pancakes which connected series by joints. electrical analysis these joints includes estimation dc resistance, calculation ac loss power, loop currents and local Joule heating during whole plasma scenario. effect a disruption is also considered. thermal performed using transient thermohydraulic two-fluid code, modeling two-channel...
Every ten years or so, Shell has looked to refresh its Advanced Process Control (APC) technology. The last major technology upgrade occurred in 2003 when along, with our APC alliance partner, Yokogawa, released SMOCPro (MPC) and RQEPro (quality estimation). In 2011, Yokogawa agreed initiate the development of next-generation Brought market 2015, Platform for Estimation (PACE) was built from ground up, leveraging long combined experience APC.
The general design and the associated performance analysis of a joint proposed by European Union for both ITER Central Solenoid Toroidal Field coils are presented. Results an extensive testing programme performed on subsize joints (scale 1/8), including DC resistance pulsed field losses measurements given discussed, as well their interaction final design. feasibility tests carried out full-cite piece also given. This study has finally led to full-size sample be fabricated in industry end...