J. Ongena

ORCID: 0000-0001-7456-4739
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About
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Research Areas
  • Magnetic confinement fusion research
  • Particle accelerators and beam dynamics
  • Fusion materials and technologies
  • Superconducting Materials and Applications
  • Ionosphere and magnetosphere dynamics
  • Laser-Plasma Interactions and Diagnostics
  • Plasma Diagnostics and Applications
  • Nuclear reactor physics and engineering
  • Nuclear Physics and Applications
  • Solar and Space Plasma Dynamics
  • Cold Fusion and Nuclear Reactions
  • Atomic and Molecular Physics
  • Antenna Design and Analysis
  • High-Energy Particle Collisions Research
  • Electrohydrodynamics and Fluid Dynamics
  • Nuclear physics research studies
  • Spacecraft and Cryogenic Technologies
  • Electromagnetic Compatibility and Measurements
  • Nuclear Materials and Properties
  • Gyrotron and Vacuum Electronics Research
  • Meteorological Phenomena and Simulations
  • Laser Design and Applications
  • Electromagnetic Scattering and Analysis
  • Advanced Antenna and Metasurface Technologies
  • Nuclear Engineering Thermal-Hydraulics

Laboratoire de Physique des Plasmas
1992-2025

Royal Military Academy
2015-2024

European Steel Association
2020

Moscow Engineering Physics Institute
2019-2020

Culham Science Centre
2004-2016

Culham Centre for Fusion Energy
2016

Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2016

École Normale Supérieure - PSL
1989-2015

Forschungszentrum Jülich
1993-2013

École nationale des ponts et chaussées
2012

10.1038/nphys3745 article EN Nature Physics 2016-05-01

The European DEMO is a pulsed device with pulse length of 2 hours. functions devoted to the heating and current drive system are: plasma breakdown, ramp-up flat-top where fusion reactions occur, control during phase, finally ramp-down. EU-DEMO project was in Pre-Concept Design Phase 2014-2020, meaning that some cases, design values precise requirements from physics point view were not yet frozen. A total 130 MW considered for all phases plasma: flat top, 30 required neoclassical tearing...

10.1016/j.fusengdes.2022.113159 article EN cc-by Fusion Engineering and Design 2022-05-23

Recent experiments on the Type I ELMy H-mode regime performed at JET with improved diagnostics have expanded range of parameters for study ELM energy and particle losses. Deviations from standard behaviour such losses in some areas operating space revealed that are correlated (density temperature) pedestal plasma before crash, while other global characteristics (such as frequency) a consequence ELM-driven flux in-between confinement. The relative loss (to energy) is found to correlate well...

10.1088/0741-3335/44/9/303 article EN Plasma Physics and Controlled Fusion 2002-08-30

This special topic describes the contents of an L mode database that has been compiled with data from Alcator C-Mod, ASDEX, DIII, DIII-D, FTU, JET, JFT-2M, JT-60, PBX-M, PDX, T-10, TEXTOR, TFTR and Tore Supra. The consists a total 2938 entries, 1881 which are in phase while 922 ohmically heated only (ohmic). Each entry contains up to 95 descriptive parameters, including global kinetic information, machine conditioning configuration. presents description variables contained therein, it also...

10.1088/0029-5515/37/9/i10 article EN Nuclear Fusion 1997-09-01

The next step in the Wendelstein stellarator line is large superconducting device 7-X, currently under construction Greifswald, Germany. Steady-state operation an intrinsic feature of stellarators, and one key element 7-X mission to demonstrate steady-state plasma conditions relevant for a fusion power plant. device, on hand, requires implementation special technologies, giving rise technical challenges during design, fabrication assembly such device. On other also physics development at...

10.1088/0029-5515/53/12/126001 article EN Nuclear Fusion 2013-11-13

Since the last IAEA Conference JET has been in operation for one year with a programmatic focus on qualification of ITER operating scenarios, consolidation design choices and preparation plasma ITER-like wall presently being installed JET. Good progress achieved, including stationary ELMy H-mode at 4.5 MA. The high confinement hybrid scenario extended to triangularity, lower ρ* pulse lengths comparable resistive time. steady-state also ν* optimized simultaneously achieve, under conditions,...

10.1088/0029-5515/51/9/094008 article EN Nuclear Fusion 2011-08-31

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

This paper summarizes the physical principles behind novel three-ion scenarios using radio frequency waves in ion cyclotron range of frequencies (ICRF). We discuss how to transform mode conversion electron heating into a new flexible ICRF technique for and fast-ion generation multi-ion species plasmas. The theoretical section provides practical recipes selecting plasma composition realize scenarios, including two equivalent possibilities choice resonant absorbers that have been identified....

10.1063/5.0021818 article EN cc-by Physics of Plasmas 2021-02-01

Plasma production in stellarators with ion cyclotron heating is complementary to the widely used electron (ECRH). The prospective light minority scenario developed and tried on Uragan-2M Large Helical Device (LHD) had been reexamined at LHD. distinctive feature of this attempt that parameters plasma produced are better than before comparable those by ECRH. This new possibility heating, if it becomes practical, motivates rethinking role stellarator machines.

10.1063/5.0248769 article EN cc-by Physics of Plasmas 2025-03-01

Stationary high energy confinement is observed on TEXTOR-94 for times limited only by the flux swing of transformer using strong edge radiation cooling. Necessary tools are feedback control radiated power and plasma content. At highest densities obtained (up to 1.2 Greenwald limit), exceeds edge-localized-mode-free H-mode scaling ITERH93-P more than 20%. β limits reached with fH89/qa≈0.6. No detrimental effect seeded impurity seen. These discharges meet many conditions necessary a fusion...

10.1103/physrevlett.77.2487 article EN Physical Review Letters 1996-09-16

Results from the first measurements of a core plasma poloidal rotation velocity (upsilontheta) across internal transport barriers (ITB) on JET are presented. The spatial and temporal evolution ITB can be followed along with upsilontheta radial profiles, providing very clear link between location steepest region ion temperature gradient localized spin-up upsilontheta. an order magnitude higher than neoclassical predictions for thermal particles in region, contrary to close agreement found...

10.1103/physrevlett.95.155003 article EN Physical Review Letters 2005-10-07

Impurity injection in the JET ELMy H-mode regime has produced high-confinement, quasi-steady-state plasmas with densities close to Greenwald density. However, at large Ar densities, a sudden loss of confinement is observed. A possible correlation between and observed MHD phenomena, both core edge plasma, was considered. The degradation coincided impurity profile peaking following disappearance sawtooth activity. In addition, density analysis confirmed that central modes prevented peaking....

10.1088/0029-5515/43/10/023 article EN Nuclear Fusion 2003-09-26

The main objective of this paper is investigation methods for reduction divertor heat loads in order to increase the lifetime tiles future fusion reactors.Special emphasis given studies transient due edge localized modes (ELMs).Two are compared: argon seeded type-I ELMy H-modes and nitrogen type-III H-modes.In both scenarios, impurity seeding leads a pedestal energy hence released by ELM.This consequentially reduces power load targets.At high radiative fractions H-modes, part that ELM (small...

10.1088/0029-5515/44/2/013 article EN Nuclear Fusion 2004-01-16

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

We report on a very efficient ion-cyclotron-resonance-frequency (ICRF) absorption scheme (Z)–Y–X, which hinges the presence of three ion species residing in plasma. A mode conversion (cutoff-resonance) layer is well known to appear two-ion plasmas. If location L-cutoff Y–X plasmas, can be controlled by varying Y : X density ratio, almost coincides with fundamental cyclotron resonance third Z (resonant absorber), latter—albeit present only trace quantities—is shown absorb all incoming RF...

10.1088/0029-5515/55/3/032001 article EN Nuclear Fusion 2015-02-06

Dedicated experiments to generate energetic D ions and fusion-born alpha particles were performed at the Joint European Torus (JET) with ITER-like wall (ILW). Using 3-ion radio frequency (RF) heating scenario, deuterium from neutral beam injection (NBI) accelerated in core of mixed plasmas higher energies ion cyclotron resonance (ICRF) waves, turn leading a core-localized source particles. The fast-ion distribution RF-accelerated D-NBI was controlled by varying ICRF NBI power ( 4–6 MW, 3–20...

10.1088/1741-4326/abb95d article EN Nuclear Fusion 2020-09-17

Wall conditioning is essential in tokamak and stellarator research to achieve plasma performance reproducibility. This paper presents an overview of recent results, both from experiments present devices modelling, view with superconducting coils, focus on W7-X, JT-60SA ITER. In these devices, the coils stay energised throughout experimental day or week which demands for new techniques that work presence nominal field, addition proven methods such as baking, glow discharge (GDC) low-Z wall...

10.1088/1361-6587/ab5ad0 article EN Plasma Physics and Controlled Fusion 2019-11-22

A model for the transition to radiatively improved (RI) mode triggered in tokamaks by seeding of impurities is proposed. This takes into account that with increasing plasma effective charge growth rate toroidal ion temperature gradient (ITG) instability, considered nowadays as dominant source anomalous energy losses low-confinement (L) mode, decreases. As a result density profile peaks due an inward convection generated trapped electron turbulence. completely quenches ITG induced transport...

10.1103/physrevlett.84.895 article EN Physical Review Letters 2000-01-31

Coating of the walls TEXTOR with silicon has led to improved tokamak plasma performance. Very low concentrations C, B, and O are measured. Radiation from is located at periphery r/a\ensuremath{\ge}0.75 decreases increasing density. Density limits enhanced by 30% as compared boronized conditions; large density gradients electron temperatures edge (10 eV) obtained. The confinement regimes observed earlier densities...

10.1103/physrevlett.71.1549 article EN Physical Review Letters 1993-09-06

Results of stability analysis are presented for two types plasma with good confinement: internal transport barriers (ITBs) on Tore Supra and the radiative improved (RI) mode TEXTOR. The has been performed an electrostatic linear gyrokinetic code, evaluating growth rates microinstabilities. code developed, KINEZERO, is aimed at systematic microstability analysis. Therefore trade-off between having perfect quantitative agreement minimizing computation time made in favour latter. In plasmas...

10.1088/0029-5515/42/7/312 article EN Nuclear Fusion 2002-07-01

An overview is given of the experimental method, analysis technique and results for trace tritium experiments conducted on JET tokamak in 2003. Observations associated with events such as sawtooth collapses, neo-classical tearing modes edge localized are described. Tritium transport seen to approach levels plasma core at high density low q(95), barrier region internal (ITB) discharges. remains well above all other cases. The correlation measured diffusion coefficient convection velocity...

10.1088/0741-3335/46/12b/022 article EN Plasma Physics and Controlled Fusion 2004-11-19

Observations of bulk plasma rotation in radio frequency (RF) heated JET discharges are reported. This study is concentrated on RF L-mode plasmas. In particular, the toroidal profiles plasmas by ion cyclotron resonance (ICRF) waves and lower hybrid (LH) have been analysed. It first time that with LH measured dedicated discharges. found outer region co-current direction irrespective heating scenario. An interesting feature profile appears to be hollow many at low current, but a current itself...

10.1088/0741-3335/51/4/044008 article EN Plasma Physics and Controlled Fusion 2009-03-18
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