A5108380435- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Laser-Plasma Interactions and Diagnostics
- High-Energy Particle Collisions Research
- Ionosphere and magnetosphere dynamics
- Nuclear physics research studies
- Atomic and Molecular Physics
- Plasma Diagnostics and Applications
- Laser-induced spectroscopy and plasma
- Cold Atom Physics and Bose-Einstein Condensates
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Atomic and Subatomic Physics Research
- Nuclear reactor physics and engineering
- Solar and Space Plasma Dynamics
- Gyrotron and Vacuum Electronics Research
- Target Tracking and Data Fusion in Sensor Networks
- Magnetic Properties and Applications
- Cosmology and Gravitation Theories
- X-ray Spectroscopy and Fluorescence Analysis
- Particle physics theoretical and experimental studies
- Statistical Mechanics and Entropy
- Electromagnetic Launch and Propulsion Technology
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2009-2020
Royal Military Academy
2020
CEA Cadarache
2008-2018
Institut de Recherche sur la Fusion par Confinement Magnétique
2018
Culham Science Centre
2014
Centre National de la Recherche Scientifique
1999-2013
Aix-Marseille Université
2009-2013
Institut National de Physique Nucléaire et de Physique des Particules
1999-2000
GANIL
1994-2000
An overview of the present status research toward final design ITER disruption mitigation system (DMS) is given. The DMS based on massive injection impurities, in order to radiate plasma stored energy and mitigate potentially damaging effects disruptions. this will be extremely challenging due many physics engineering constraints such as limitations port access amount species injected impurities. Additionally, questions relevant remain unsolved mechanisms for mixing assimilation impurities...
Experimental data obtained with the $4\ensuremath{\pi}$ multidetector system INDRA are used to study midvelocity emissions of light charged particles (LCP) and intermediate mass fragments for peripheral semicentral collisions Xe Sn at energies between 25 50 MeV/nucleon. The analysis is performed as a function incident energy impact parameter, defined through total transverse LCP. onset found be close Evaporative processes also identified sensitive parameter but show, given little dependence...
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...
A new ITER-relevant lower hybrid current drive (LHCD) launcher, based on the passive-active-multijunction (PAM) concept, was brought into operation Tore Supra tokamak in autumn 2009. The PAM launcher concept designed view of ITER to allow efficient cooling waveguides, as required for long pulse operation. In addition, it offers low power reflection close cut-off density, which is very attractive ITER, where large distance between plasma and wall may bring density front values. first...
Recently, reversed magnetic shear operation was performed using only ion-cyclotron-resonance frequency minority heating (ICRH) during current ramp-up. A wide region of has been obtained. For the first time, an electron internal transport barrier sustained by ICRH is observed, with a dramatical drop density fluctuations. This maintained, on flat top, for about 2 s.
Realizing high-power long-duration discharges puts specific constraints on diagnostics: Their front parts have to withstand important thermal loads, eventually requiring active cooling of critical parts, and drifts in measurements be avoided order supply reliable measurement during the whole discharge duration. Furthermore, importance diagnostics for missions other than physics understanding, such as machine operation or safety control, increases. The system Tore Supra consists roughly 30...
ECRH pre-ionization and assisted start-up will be necessary in ITER due to the low electric field available (⩽0.3 V m −1 ). This paper reports on results recently obtained at fundamental EC resonance tokamak Tore Supra ( B T = 3.85 T, R 2.4 m, a 0.72). The ECRH/ECCD system is based two 118 GHz gyrotrons (EC ∼ 2.17 m). power injected into plasma as Gaussian beams by an antenna located side which, using actively cooled mirrors inside vacuum vessel, allows extensive control of both poloidal...
Issues related to the limitations and optimization of long pulse operation at high radiofrequency (RF) power levels in Tore Supra tokamak are presented. An increasing operational limitation was encountered during experimental campaigns 2006–2007, affecting performance. This characterized by sudden appearance a multifaceted asymmetric radiation from edge (MARFE), often followed disruption. The analyses revealed that could be linked over-heating flaking carbon re-deposition layers on main...
Abstract Efforts to provide regular, automatic, and reliable reciprocating probe measurements in the scrape‐off layer of Tore Supra tokamak are described. Real time feedback on fast magnetic reconstruction is used control position relative last closed flux surface, while analysis current‐voltage characteristics adapt voltage waveform applied probe, improving dynamic range measurement. A large head employed ensure operation strongly magnetized plasma regime. Concave collectors embedded head,...
The Tore Supra tokamak is devoted to long-duration, high-performance plasma research. real-time measurements and control (RTMC) system has been developed address the basic controls, such as equilibrium density control. Over years, more sophisticated demanding controls have implemented, allowing improvement of performance machine protection. This includes current profile enhance avoid magnetohydrodynamic instabilities, infrared monitoring plasma-facing components prevent overheating,...
The WEST tokamak consists of a major upgrade the superconducting medium size Tore Supra aiming at testing ITER divertor components. Such modification has required rebuilding full set magnetic diagnostics. project was started in 2013 and completed 2016. diagnostic 469 sensors (421 pick-up coils, 36 flux loops, 12 Rogowski coils) installed vacuum vessel. New analog integrators have been developed order to obtain field from raw signal sensors. During startup phase WEST, plasma currents few kilo...
A short review of diagnostics and techniques for active power exhaust control is given from the point view experiences gained at Tore Supra. The physical technological aspects are presented with aim illustrating strengths, difficulties potential future long pulse steady state fusion devices such as W7X ITER-FEAT. One main features Supra approach to reliance on infrared (IR) thermography survey nearly 100% high flux target zones. This applied largest elements, toroidal pump limiter heating...