D. Guilhem
A5004870936- Magnetic confinement fusion research
- Fusion materials and technologies
- Particle accelerators and beam dynamics
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Gyrotron and Vacuum Electronics Research
- Nuclear reactor physics and engineering
- Ionosphere and magnetosphere dynamics
- Nuclear Physics and Applications
- Particle Accelerators and Free-Electron Lasers
- Nuclear Materials and Properties
- Electromagnetic Launch and Propulsion Technology
- Pulsed Power Technology Applications
- Atomic and Molecular Physics
- Antenna Design and Analysis
- Calibration and Measurement Techniques
- Metal and Thin Film Mechanics
- Gas Dynamics and Kinetic Theory
- Ion-surface interactions and analysis
- Advanced materials and composites
- Thermography and Photoacoustic Techniques
- Fluid Dynamics and Turbulent Flows
- Laser-induced spectroscopy and plasma
- Spacecraft and Cryogenic Technologies
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2012-2021
CEA Cadarache
2012-2021
Institut de Recherche sur la Fusion par Confinement Magnétique
1998-2021
DSM (Netherlands)
2012
Korea Institute of Fusion Energy
2011
Culham Science Centre
1986-2011
ITER
2009-2011
Southwestern Institute of Physics
2011
National Agency for New Technologies, Energy and Sustainable Economic Development
2011
Culham Centre for Fusion Energy
1984-2011
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...
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:...
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...
A 20 MW/5 GHz lower hybrid current drive (LHCD) system was initially due to be commissioned and used for the second mission of ITER, i.e. Q = 5 steady state target. Though not part currently planned procurement phase, it is now under consideration an earlier delivery. In this paper, both physics technology conceptual designs are reviewed. Furthermore, appropriate work plan also developed. This design, R&D, installation a MW LHCD on ITER follows Scientific Technical Advisory Committee...
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...
Plasma Facing Components (PFC) temperature measurement is mandatory to ensure safe high power and long pulse tokamak operation. IR thermography systems which are widely used in magnetic fusions devices become challenged with the choice of tungsten as a PFC material ITER tokamak, mainly due emissivity uncertainties reflection issues hot environment. Embedded measurements foreseen cross-check measurements. Fiber Bragg grating sensors potentially great interest for this application because they...
As a result of experimental observations localized heat flux on components magnetically connected to radiating waveguides in Tore Supra and TdeV, the acceleration electrons near lower hybrid (LH) antennas has been investigated. A simple analytical model developed compute dynamics particles field approximation. Landau damping very high N|| (20 < 100) component launched spectrum thermal scrape-off layer (SOL) is found occur. Simulation typical LH pulse indicates that can be accelerated up 2-3...
A new concept of lower hybrid antenna for current drive has been proposed ITER (Bibet et al 1995 Nucl. Fusion 35 1213–23 ): the passive active multijunction (PAM) that relies on a periodic combination and waveguides. An actively cooled PAM at 3.7 GHz recently installed tokamak Tore Supra. This paper summarizes comprehensive experimental characterization coupling properties to Supra plasmas. In this paper, electromagnetic are measured reduced power (<1 MW) allow systematic comparison with...
Abstract In the framework of ion cyclotron resonance heating (ICRH) development led at CEA Cadarache, an actively cooled Faraday screen (FS) prototype with cantilevered horizontal bars and a slotted box has been designed to increase heat exhaust capability (for high-power operation), reduce parallel RF electric field along long lines qualify alternative mechanical solutions for ITER (bars are disconnected from septum stress level). The new FS installed on existing ICRH antenna, was tested...
W/Cu flat-type plasma facing components (PFCs) were widely used in divertor of fusion device because its advantages, such as low cost, light weight and good machinability. However, it is very difficult to manufacture them due the large mismatch between thermo-mechanical properties W Cu. Institute Plasma Physics, Chinese Academy Sciences (ASIPP) has successfully developed PFCs for EAST project by hot isostatic pressing (HIP) technology. This paper presents development application at ASIPP....
In view of high-power, long-pulse steady-state operation, Tore Supra has incorporated in its design the active control heat and particles a realistic environment. early experimental phase Supra, first generation plasma-facing components was tested, these tests provided much physics technological information illuminated various operational difficulties. particular, experiments revealed weakness graphite-to-metal brazing process originally adopted for actively cooled high-heat-flux components....
TORE SUPRA is a large superconducting tokamak designed for sustaining long inductive pulses (t approximately 30 s). In particular, all the first wall components have been steady-state heat and particle exhaust, injection, additional heating. addition to these technological assets, strict control of plasma-wall interactions required. This has done at low power: experiments with ohmic heating mainly devoted pump limiter, ergodic divertor pellet injection experiments. Some specific problems...
The main results of the Tore Supra experimental programme in years 2007–2008 are reported. They document significant progress achieved domain steady-state tokamak research, as well more general issues relevant for ITER and fusion physics research. Three areas covered: technology developments tests a real machine environment, operational high power long pulses, plasma physics. Results presented this paper include test validation new, load-resilient concept ion cycotron resonance heating...