L. Colas

ORCID: 0000-0002-4573-3326
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About
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Research Areas
  • Magnetic confinement fusion research
  • Particle accelerators and beam dynamics
  • Ionosphere and magnetosphere dynamics
  • Superconducting Materials and Applications
  • Fusion materials and technologies
  • Plasma Diagnostics and Applications
  • Laser-Plasma Interactions and Diagnostics
  • Gyrotron and Vacuum Electronics Research
  • Nuclear reactor physics and engineering
  • Solar and Space Plasma Dynamics
  • Antenna Design and Analysis
  • Electromagnetic Simulation and Numerical Methods
  • Lightning and Electromagnetic Phenomena
  • Pulsed Power Technology Applications
  • Laser-induced spectroscopy and plasma
  • Electrostatic Discharge in Electronics
  • Electromagnetic Compatibility and Measurements
  • High voltage insulation and dielectric phenomena
  • Microwave and Dielectric Measurement Techniques
  • Electromagnetic Launch and Propulsion Technology
  • Non-Destructive Testing Techniques
  • Full-Duplex Wireless Communications
  • Semiconductor materials and interfaces
  • Dust and Plasma Wave Phenomena
  • Nuclear Physics and Applications

CEA Cadarache
2016-2025

Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2015-2025

Université Grenoble Alpes
2025

CEA LETI
2025

Institut de Recherche sur la Fusion par Confinement Magnétique
2008-2022

Royal Military Academy
2020

CEA Grenoble
2017

Culham Science Centre
2009-2016

Culham Centre for Fusion Energy
2016

Japan External Trade Organization
2015

CRONOS is a suite of numerical codes for the predictive/interpretative simulation full tokamak discharge. It integrates, in modular structure, 1D transport solver with general 2D magnetic equilibria, several heat, particle and impurities models, as well momentum sources. This paper gives first comprehensive description suite: overall structure code, main available details on workflow implementation. Some examples applications to analysis experimental discharges predictions ITER scenarios are...

10.1088/0029-5515/50/4/043001 article EN Nuclear Fusion 2010-03-16

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:...

10.1088/0029-5515/55/6/063017 article EN cc-by Nuclear Fusion 2015-05-06

Abstract WEST is an MA class superconducting, actively cooled, full tungsten (W) tokamak, designed to operate in long pulses up 1000 s. In support of ITER operation and DEMO conceptual activities, key missions are: (i) qualification high heat flux plasma-facing components integrating both technological physics aspects relevant particle exhaust conditions, particularly for the monoblocks foreseen divertor; (ii) integrated steady-state at confinement, with a focus on power issues. During phase...

10.1088/1741-4326/ac2525 article EN cc-by Nuclear Fusion 2021-09-09

Abstract Ion cyclotron resonance frequency (ICRF) heating has been an essential component in the development of high power H-mode scenarios Jet European Torus ITER-like wall (JET-ILW). The ICRF performance was improved by enhancing antenna-plasma coupling with dedicated main chamber gas injection, including preliminary minimization RF-induced plasma-wall interactions, while RF where optimized for core impurity screening terms ion position and minority hydrogen concentration. impact on...

10.1088/0029-5515/56/3/036022 article EN Nuclear Fusion 2016-02-19

A comparison of the ASDEX Upgrade 3-strap ICRF antenna data with linear electromagnetic TOPICA calculations is presented.The substantiates a reduction local electric field at radially protruding plasma-facing elements as relevant approach for minimizing tungsten (W) sputtering in conditions when slow wave strongly evanescent.The measured reaction time-averaged RF current limiters to feeding variations less sensitive than predicted by calculations.This likely have been caused temporal and...

10.1088/0741-3335/59/1/014022 article EN Plasma Physics and Controlled Fusion 2016-10-27

In JET, lower hybrid (LH) and ion cyclotron resonance frequency (ICRF) wave absorption in the scrape-off layer can lead to enhanced heat fluxes on some plasma facing components (PFCs). Experiments have been carried out characterize these loads order to: (i) prepare JET operation with Be wall which has a reduced power handling capability as compared carbon (ii) better understand physics driving phenomena propose solutions for next generation systems reduce them. When using ICRF, hot spots are...

10.1088/0029-5515/51/10/103018 article EN Nuclear Fusion 2011-08-31

A minimal two-field fluid approach is followed to describe the radio-frequency (RF) wave propagation in bounded scrape-off layer plasma of magnetic fusion devices self-consistently with direct current (DC) biasing this plasma. The RF and DC parts are coupled by non-linear sheath boundary conditions at both ends open field lines. physical model studied within a simplified framework featuring slow (SW) only lateral walls normal straight confinement field. possibility however kept excite system...

10.1063/1.4750046 article EN Physics of Plasmas 2012-09-01

During the 2011 experimental campaign, one of three ion cyclotron resonance heating (ICRH) antennas in Tore Supra tokamak was equipped with a new type Faraday screen (FS). The design aimed at minimizing integrated parallel electric field over long lines as well increasing heat exhaust capability actively cooled screen. It proved to be inefficient for attenuating radio-frequency (RF)-sheaths on itself contrary concept that allowed operation despite higher fluxes antenna. In parallel, approach...

10.1063/1.4884778 article EN Physics of Plasmas 2014-06-01

Abstract Experiments on ASDEX Upgrade (AUG) in 2021 and 2022 have addressed a number of critical issues for ITER EU DEMO. A major objective the AUG programme is to shed light underlying physics confinement, stability, plasma exhaust order allow reliable extrapolation results obtained present day machines these reactor-grade devices. Concerning pedestal physics, mitigation edge localised modes (ELMs) using resonant magnetic perturbations (RMPs) was found be consistent with reduction linear...

10.1088/1741-4326/ad249d article EN cc-by Nuclear Fusion 2024-01-31

The Alfvén instability nonlinearly excited the energetic-particle-driven geodesic acoustic mode on ASDEX-Upgrade tokamak, as demonstrated experimentally. mechanism of excitation and nonlinear evolution is not yet fully understood. In present work, a first-principles simulation using MEGA code investigated properties in both linear growth saturated phases. Here we show that successfully reproduced coexistence these two modes, agreed with experimental results well. Conclusive evidence showed...

10.1038/s41598-024-82577-3 article EN cc-by-nc-nd Scientific Reports 2025-01-07

Indium phosphide (InP) semiconductor technology is being explored for radiofrequency (RF) applications, targeting frequencies exceeding 100 GHz, to support the next generation of 6G communication systems. When taking into account sustainability in designing this future generation, growing concerns are emerging regarding environmental impact networks and reliance on raw materials production Information Communication Technologies (ICTs). The extraction, processing, manufacturing such...

10.3390/su17031339 article EN Sustainability 2025-02-06

Abstract For successfully heating plasma with waves in the Ion Cyclotron Range of Frequencies (ICRF), mitigating impurity production is just as crucial maximizing power coupling, especially high-Z environments [Urbanczyk 2021]. Only when coupled limited influence on production, can ICRF truly become a powerful tool to directly deposit energy ions, modify turbulence-driven transport and enhance efficiency fusion reactions. 
To do so, one must rely toroidal array at least three active...

10.1088/1741-4326/adbd52 article EN cc-by Nuclear Fusion 2025-03-06

Abstract On the basis of several recent breakthroughs in fusion research, many activities have been launched around world to develop power plants on fastest possible time scale. In this context, high-fidelity simulations plasma behavior large supercomputers provide one main pathways accelerating progress by guiding crucial design decisions. When it comes determining energy confinement a magnetic device, which is key quantity interest, gyrokinetic turbulence are considered approach choice –...

10.1038/s41467-025-56997-2 article EN cc-by Nature Communications 2025-03-15

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...

10.1088/0029-5515/42/10/308 article EN Nuclear Fusion 2002-09-16

Recent achievements in studies of the effects ICRF (Ion Cyclotron Range Frequencies) power on SOL (Scrape-Off Layer) and PWI (Plasma Wall Interactions) ASDEX Upgrade (AUG), Alcator C-Mod, JET-ILW are reviewed. Capabilities to diagnose model effect DC biasing associated impurity production at active antennas magnetic field connections described. The experiments show that near-fields can lead not only E × B convection, but also modifications density, which for C-Mod limited a narrow region...

10.1016/j.nme.2018.11.017 article EN cc-by-nc-nd Nuclear Materials and Energy 2018-12-20

Within the EUROfusion MST1 work package, a series of experiments has been conducted on AUG and TCV devices to disentangle role plasma fueling shape for onset small ELM regimes. On both devices, regimes with high confinement are achieved if only two conditions fulfilled at same time. Firstly, density separatrix must be large enough (), leading pressure profile flattening separatrix, which stabilizes type-I ELMs. Secondly, magnetic configuration close double null (DN), reduction shear in...

10.1088/1741-4326/ab2211 article EN Nuclear Fusion 2019-05-16

Integrating the plasma core performance with an edge and scrape-off layer (SOL) that leads to tolerable heat particle loads on wall is a major challenge. The new European medium size tokamak task force (EU-MST) coordinates research ASDEX Upgrade (AUG), MAST TCV. This multi-machine approach within EU-MST, covering wide parameter range, instrumental progress in field, as ITER DEMO core/pedestal SOL parameters are not achievable simultaneously present day devices. A two prong adopted. On one...

10.1088/1741-4326/aa6084 article EN cc-by Nuclear Fusion 2017-06-28

Abstract The ASDEX Upgrade (AUG) programme, jointly run with the EUROfusion MST1 task force, continues to significantly enhance physics base of ITER and DEMO. Here, full tungsten wall is a key asset for extrapolating future devices. high overall heating power, flexible mix comprehensive diagnostic set allows studies ranging from mimicking scrape-off-layer divertor conditions DEMO at density fully non-inductive operation ( q 95 = 5.5, ) low density. Higher installed electron cyclotron...

10.1088/1741-4326/ab18b8 article EN cc-by Nuclear Fusion 2019-04-12

In this paper we validate the finite element code RAPLICASOL, which models radiofrequency wave propagation in edge plasmas near ICRF antennas, against calculations with TOPICA code. We compare output of both codes for ASDEX Upgrade 2-strap antenna, and a 4-strap WEST-like antenna. Although RAPLICASOL requires considerably fewer computational resources than TOPICA, find that predicted quantities experimental interest (including reflection coefficients, coupling resistances, - -matrix entries,...

10.1088/1741-4326/aaf455 article EN Nuclear Fusion 2018-11-27

Abstract As part of ITPA-Integrated Operational Scenario activities, this contribution reviews recent experimental characterizations radio-frequency (RF)-induced scrape-off layer (SOL) modifications various tokamaks worldwide and the LArge Plasma Device at UCLA. The phenomenology, as observed using a large variety measurement techniques, is consistent with expectations from RF sheath rectification. Emphasis then put on complex three-dimensional (3D) spatial patterns RF–SOL interaction, in...

10.1088/1741-4326/ac35f9 article EN Nuclear Fusion 2021-11-03

The two-dimensional (2D) edge plasma density distribution in the scrape off layer magnetically connected to ion cyclotron resonance heating (ICRH) antennae is studied experimentally and numerically tokamak Tore Supra. A local decrease front of loaded ICRH antenna (“pump-out” effect) demonstrated by Langmuir probe measurements a low recycling regime. An up–down asymmetry heat-flux erosion also observed, associated with poloidal variations density. These redistributions are ascribed an E×B...

10.1063/1.1472501 article EN Physics of Plasmas 2002-05-21

For the first time, internal magnetic turbulence is measured by a new cross polarization scattering diagnostic in Tore Supra tokamak. The principle of this experiment presented. It based on change or mode conversion electromagnetic wave scattered fluctuations. A strong correlation between fluctuation and additional heating observed, contrary to edge observed fluctuations increase linearly with poloidal beta number ${\ensuremath{\beta}}_{p}$ L-mode confinement regime.

10.1103/physrevlett.75.1090 article EN Physical Review Letters 1995-08-07

Ion cyclotron resonance heating (ICRH) in the hydrogen minority scheme provides central ion and acts favorably on core tungsten transport. Full wave modeling shows that, at medium power level (4 MW), after collisional redistribution, ratio of transferred to ions electrons vary little with (hydrogen) concentration nH/ne but high-Z impurity screening provided by fast temperature increases concentration. The radiated JET discharges has been analyzed a large database covering 2013–2014 campaign....

10.1088/1361-6587/aa60d2 article EN Plasma Physics and Controlled Fusion 2017-02-16
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