A5018219278- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Ionosphere and magnetosphere dynamics
- Laser-Plasma Interactions and Diagnostics
- Magneto-Optical Properties and Applications
- Advanced Fiber Optic Sensors
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Nuclear Physics and Applications
- Plasma Diagnostics and Applications
- Radiation Effects in Electronics
- Gyrotron and Vacuum Electronics Research
- Photonic and Optical Devices
- Atomic and Subatomic Physics Research
- Photoacoustic and Ultrasonic Imaging
- Integrated Circuits and Semiconductor Failure Analysis
- Magnetic Field Sensors Techniques
- Optical Coherence Tomography Applications
- Lightning and Electromagnetic Phenomena
- Ion-surface interactions and analysis
- Physics of Superconductivity and Magnetism
- Terahertz technology and applications
- Solar and Space Plasma Dynamics
CEA Cadarache
2016-2025
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2016-2025
Institut de Recherche sur la Fusion par Confinement Magnétique
2011-2024
General Atomics (United States)
2024
CEA Grenoble
2022
Université Grenoble Alpes
2020
Laboratoire Interdisciplinaire de Physique
2020
Centre National de la Recherche Scientifique
2009-2020
Direction de la Recherche Technologique
2012
Southwestern Institute of Physics
2011
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:...
This paper proposes a control-oriented approach to the tokamak plasma current profile dynamics. It is established based on consistent set of simplified relationships, in particular for microwave drive sources, rather than exact physical modelling. Assuming that proper model advanced control schemes can be using so-called cylindrical approximation and neglecting diamagnetic effects, we propose focuses flux diffusion (from which inferred). Its inputs are some real-time measurements available...
Disruptions are a major threat for future tokamaks, including ITER. Disruption-generated heat loads, electromagnetic forces and runaway electrons will not be tolerable next-generation devices. Massive noble gas injection is foreseen as standard mitigation system these tokamaks. Disruption experiments have been carried out on Tore Supra to study various scenarios investigate jet penetration mixing. Comparisons of different gases (He, Ne, Ar, He/Ar mixture) amounts (from 5 500 Pa m 3 ) were...
Abstract Using a recently installed impurity powder dropper (IPD), boron (<150 μ m) was injected into lower single null (LSN) L-mode discharges in WEST. IPDs possibly enable real-time wall conditioning of the plasma-facing components and may help to facilitate H-mode access full-tungsten environment The this experiment featured I p = 0.5 MA, B T 3.7 T, q 95 4.3, t pulse 12–30 s, n e,0 ∼ 4 × 10 19 m −2 , P LHCD 4.5 MW. Estimates deuterium particle fluxes, derived from combination visible...
Abstract The choice of first wall material is paramount importance for the plasma start-up conditions in ITER and future fusion power plants. In this context, present work focuses on correlations between impurity sources total radiated during tungsten (W) Environment Steady-state Tokamak (WEST). objective to highlight experimental indications a preferable combination scenario materials. Until 2019, WEST featured full high Z with all limiters exposing only W surfaces plasma. To study impact...
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...
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...
Abstract This paper summarizes the emissivity measurements performed on plasma-facing units (PFU) of WEST lower divertor during first phase running with a mix actively cooled ITER-like PFUs made bulk tungsten (W) and inertially graphite coating tungsten. In situ assessments laboratory after removing W-coated ITER-grade from device are shown. The exhibit complex pattern strong variation as function space time mainly explained magnetic equilibrium (strike point location) well plasma...
In a tokamak plasma, sawtooth oscillations in the central temperature, caused by magnetohydrodynamic instability, can be partially stabilized fast ions. The resulting less frequent crashes trigger unwanted activity. This Letter reports on experiments showing that modest electron-cyclotron current drive power, with deposition positioned feedback control of injection angle, reliably shorten period presence ions energies $\ensuremath{\ge}0.5\text{ }\text{ }\mathrm{MeV}$. Certain surprising...
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....
This paper describes what we can learn on the regimes of spontaneous electron temperature oscillations discovered in Tore Supra from analysis MHD activity. Since first observations this oscillating behaviour plasma equilibrium, and its interpretation as a predator–prey system involving lower hybrid waves power deposition confinement, modes has confirmed reality safety factor profile oscillations. points towards importance rational values transition to transport barriers reversed magnetic...
In this paper, we compare, by means of simulations using the Jones formalism, performances several optical fiber types (low birefringence and spun fibers) for measurement plasma current in international thermonuclear experimental reactor (ITER). The main results presented paper concern minimum value ratio between beat length period, which allows meeting ITER specifications. Assuming a high-birefringence with 3 mm, demonstrate that period is 4.4 when considering 28 m long sensing surrounding...
An overview of the preliminary design ITER plasma control system (PCS) is described here, which focusses on needs for 1st and early operation in hydrogen/helium (H/He) up to a current 15 MA with moderate auxiliary heating power low confinement mode (L-mode). Candidate schemes basic magnetic control, including divertor kinetic electron density gas puffing pellet injection, were developed. Commissioning systems included as well support functions stray field topology real-time boundary...
In this paper, a method was developed to estimate in-situ the emissivity of W-coated graphite divertor tiles in WEST tokamak. This is based on double heating and take advantages temperature increase after successive plasma experiments due inertial behavior facing components. Photonic calculations have been used disentangle emitted reflected parts measured radiances from infrared system. The uncertainty as well robustness investigated thanks wide IR thermocouple coverage divertor. results...
The ITER plasma control system (PCS) has successfully completed its final design for the first (FP) and engineering operations (EOs) phase plant commissioning begun as prepares this operation phase. Commissioning of essential systems will continue each is made ready operation. Tokamak assembly with base lower cylinder cryostat most poloidal field (PF) coil installed in tokamak pit. vacuum vessel (VV) sector accompanying two toroidal (TF) coils are being prepared transfer to Once assembled,...
The paper deals with radiation resistant sensors and their associated measuring instrumentation developed in the course of R D activities carried out framework an international collaboration. first trial tests three-dimensional (3D) probes Hall have been performed European tokamaks TORE SUPRA (2004) JET (2005). Later 2009 six sets 3D were installed now continue to operate. statistical analysis 2014 on basis database demonstrated stable long term operation all 18 probes. results measurements...