É. Belonohy

ORCID: 0000-0002-1045-4634
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About
Contact & Profiles
Research Areas
  • Magnetic confinement fusion research
  • Fusion materials and technologies
  • Superconducting Materials and Applications
  • Particle accelerators and beam dynamics
  • Nuclear reactor physics and engineering
  • Laser-Plasma Interactions and Diagnostics
  • Ionosphere and magnetosphere dynamics
  • Nuclear Materials and Properties
  • Nuclear Physics and Applications
  • High-Energy Particle Collisions Research
  • Nuclear Engineering Thermal-Hydraulics
  • Mining and Gasification Technologies
  • Plasma Diagnostics and Applications
  • Geomagnetism and Paleomagnetism Studies
  • Solar and Space Plasma Dynamics
  • Iron and Steelmaking Processes
  • Dust and Plasma Wave Phenomena
  • Computational Fluid Dynamics and Aerodynamics
  • Fault Detection and Control Systems
  • Diversity and Career in Medicine
  • Cyclone Separators and Fluid Dynamics
  • Particle Detector Development and Performance
  • Plasma and Flow Control in Aerodynamics
  • Aerodynamics and Acoustics in Jet Flows
  • Atomic and Subatomic Physics Research

Culham Science Centre
2014-2024

Max Planck Institute for Plasma Physics
2011-2024

United Kingdom Atomic Energy Authority
2021-2024

National Centre of Scientific Research "Demokritos"
2021

Culham Centre for Fusion Energy
2017-2021

Royal Military Academy
2020

Max Planck Society
2010-2017

Fusion for Energy
2015

Institute for Particle and Nuclear Physics
2008

Hungarian Academy of Sciences
2006-2008

Abstract The JET 2019–2020 scientific and technological programme exploited the results of years concerted engineering work, including ITER-like wall (ILW: Be W divertor) installed in 2010, improved diagnostic capabilities now fully available, a major neutral beam injection upgrade providing record power 2019–2020, tested technical procedural preparation for safe operation with tritium. Research along three complementary axes yielded wealth new results. Firstly, plasma delivered scenarios...

10.1088/1741-4326/ac47b4 article EN cc-by Nuclear Fusion 2022-01-04

The 2014–2016 JET results are reviewed in the light of their significance for optimising ITER research plan active and non-active operation. More than 60 h plasma operation with first wall materials successfully took place since its installation 2011. New multi-machine scaling type I-ELM divertor energy flux density to is supported by principle modelling. relevant disruption experiments modelling reported a set three mitigation valves mimicking setup. Insights L–H power threshold Deuterium...

10.1088/1741-4326/aa5e28 article EN cc-by Nuclear Fusion 2017-06-15

The dependence of plasma transport and confinement on the main hydrogenic ion isotope mass is fundamental importance for understanding turbulent and, therefore, accurate extrapolations from present tokamak experiments, which typically use a single hydrogen isotope, to burning plasmas such as ITER, will operate in deuterium–tritium mixtures. Knowledge properties edge barrier formation species critical view initial, low-activation phase ITER operations or helium its implications subsequent...

10.1088/1361-6587/aa9901 article EN Plasma Physics and Controlled Fusion 2017-11-08

Abstract For the past several years, JET scientific programme (Pamela et al 2007 Fusion Eng. Des . 82 590) has been engaged in a multi-campaign effort, including experiments D, H and T, leading up to 2020 first with 50%/50% D–T mixtures since 1997 ever plasmas ITER mix of plasma-facing component materials. this purpose, concerted physics technology was launched view prepare campaign (DTE2). This paper addresses key elements developed by directly contributing preparation. intense preparation...

10.1088/1741-4326/ab2276 article EN cc-by Nuclear Fusion 2019-05-17

Abstract The JET hybrid scenario has been developed from low plasma current carbon wall discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with ITER-like Be/W wall. development started pure Deuterium refinement of current, and toroidal magnetic field choices succeeded solving heat load challenges arising 37 MW injected power ITER like environment, keeping radiation edge core controlled, avoiding MHD instabilities reaching high neutron rates. have re-run Tritium...

10.1088/1741-4326/acde8d article EN cc-by Nuclear Fusion 2023-10-12

Disruptions are a major operational concern for next generation tokamaks, including ITER.They may generate excessive heat loads on plasma facing components, large electromagnetic forces in the machine structures and several MA of multi-MeV runaway electrons.A more complete understanding processes methods to suppress them is necessary ensure safe reliable operation future tokamaks.Runaway electrons were studied at JET-ILW showing that their dependencies (accelerating electric field, avalanche...

10.1088/0029-5515/55/9/093013 article EN Nuclear Fusion 2015-08-05

Abstract ITER is of key importance in the European fusion roadmap as it aims to prove scientific and technological feasibility a future energy source. The EUROfusion consortium labs within Europe contributing preparation exploitation operation aspires exploit outcomes view DEMO. paper provides an overview major progress obtained recently, carried out frame new (initiated 2021) work-package called ‘ Pr eparation I TER O peration’ (PrIO). directly supported by eleven PrIO contributions given...

10.1088/1741-4326/ad346e article EN cc-by Nuclear Fusion 2024-03-15

The objective of thermonuclear fusion consists producing electricity from the coalescence light nuclei in high temperature plasmas. most promising route to envisages confinement such plasmas with magnetic fields, whose studied configuration is tokamak. Disruptions are catastrophic collapses affecting all tokamak devices and one main potential showstoppers on a commercial reactor. In this work we report how, deploying innovative analysis methods thousands JET experiments covering isotopic...

10.1038/s41467-024-46242-7 article EN cc-by Nature Communications 2024-03-18

The fusion energy research and development landscape has seen significant advances in recent years, with important scientific technological breakthroughs a rapid rise of investment the private sector. workforce needs nascent industry are growing at rate that academic programs not currently able to match. This paper presents findings Workforce Accelerator for Fusion Energy Development Conference held Hampton, Virginia, United States America (USA), on May 29-30 2024, which was funded by US...

10.48550/arxiv.2501.03372 preprint EN arXiv (Cornell University) 2025-01-06

A new pellet injection system was installed at JET designed for both fuelling and ELM pacing. The purpose of the pacing section to validate as a suitable tool mitigation in ITER. Pellet confirmed large size scale JET. dynamics triggered ELMs investigated with respect their spontaneous counterparts. Triggered show features also typical several operational regimes. Since none these regimes unsettled by pellets this is strong hint compatibility other plasma control tools. Observations modelling...

10.1088/0029-5515/51/3/033010 article EN Nuclear Fusion 2011-03-01

Recent experiments at ASDEX Upgrade demonstrate the compatibility of ELM mitigation by magnetic perturbations with efficient particle fuelling inboard pellet injection. persists in a high-density, high-collisionality regime even strongest applied perturbations. Pellets injected into phases trigger no type-I ELM-like events unlike when launched unmitigated ELMy plasmas. Furthermore, absence ELMs results improved efficiency and persistent density build-up. Pellet injection is helpful to access...

10.1088/0029-5515/52/2/023017 article EN Nuclear Fusion 2012-01-27

The medium size divertor tokamak ASDEX Upgrade (major and minor radii 1.65 m 0.5 m, respectively, magnetic-field strength 2.5 T) possesses flexible shaping versatile heating current drive systems. Recently the technical capabilities were extended by increasing electron cyclotron resonance (ECRH) power, installing 2 × 8 internal magnetic perturbation coils, improving ion range of frequency compatibility with tungsten wall. With reliable suppression large type-I edge localized modes (ELMs)...

10.1088/0029-5515/53/10/104003 article EN Nuclear Fusion 2013-09-26

During the 2015-2016 JET campaigns many efforts have been devoted to exploration of high-performance plasma scenarios envisaged for DT operation in JET.In this paper we review various key recent hybrid discharges and model combined ICRF+NBI heating.These deuterium with beams had ICRF antenna frequency tuned match cyclotron minority H at centre tokamak coinciding second harmonic resonance D. The modelling takes into account synergy between NBI heating through D beam ions which allows us...

10.1088/1741-4326/aad9ad article EN Nuclear Fusion 2018-08-13

Recent experiments with the ITER-like wall have demonstrated that changes in divertor strike point position are correlated strong modification of global energy confinement.The impact on confinement is observable both pedestal and core normalised gradients.The corner configuration shows an increased density gradient length ion pressure indicating a better study neutral re-circulation indicates main chamber varies inversely correlation between total can be established.It does not appear charge...

10.1088/1741-4326/aa6e1c article EN Nuclear Fusion 2017-06-30

Abstract Geodesic acoustic modes (GAMs) have been investigated in JET ohmic discharges using mainly Doppler backscattering. Characteristics and scaling properties of the GAM are studied. Time spatial resolved measurements perpendicular velocity indicate that GAMs located a narrow layer at edge density gradient region with amplitude corresponding to about 50% mean local velocity. on appear be regulated by turbulence drive rather than their damping rate. It is also shown ~20% larger deuterium...

10.1088/0029-5515/56/10/106026 article EN Nuclear Fusion 2016-08-19

Deliberate periodic movement (sweeping) of the high heat flux divertor strike lines in tokamak plasmas can be used to manage fluxes experienced by exhaust handling plasma facing components, spreading loads over a larger surface area. Sweeping has recently been adopted as routine part main performance configurations on JET, and enabled pulses with 30 MW heating power 10 radiation run for 5 s without overheating tiles. We present analysis effectiveness sweeping temperature control using...

10.1088/1402-4896/aa8db1 article EN Physica Scripta 2017-10-24

JET components are removed periodically for surface analysis to assess material migration and fuel retention. This paper describes issues related handling procedures preparing samples analysis; in particular a newly developed procedure cutting beryllium tiles is presented. Consideration also given the hazards likely due increased tritium inventory activation from 14 MeV neutrons following planned TT DT operations (DTE2) 2017. Conclusions drawn as feasibility of post DTE2.

10.1088/0031-8949/t167/1/014057 article EN Physica Scripta 2016-01-25

Abstract JET, the world’s largest operating tokamak with unique Be/W wall and tritium handling capability, completed a Deuterium-Tritium (D-T) campaign in 2021 (Maggi et al 29th Fusion Energy Conf. ) following decade of preparatory experiments, dedicated enhancements, technical rehearsals training (Horton 2016 Eng. Des. 109–111 925). Operation raises significant technical, safety scientific challenges not encountered standard protium or deuterium operation. This contribution describes...

10.1088/1741-4326/ad6ce5 article EN cc-by Nuclear Fusion 2024-08-22

To get a deeper insight into the MHD activity triggered by pellets we extended our previous analyses of standard type-I ELMs to injected discharge phases following types: Ohmic, L-mode, type-III ELMy H-mode, ELM-free, radiative edge scenarios with ELMs, quiescent H (QH)-mode regime. It turns out that pellet injection generally creates strong local perturbation equilibrium in ablation region and even beyond. Regarding triggering this initial can damp out, indicating plasma is stable...

10.1088/0029-5515/48/9/095007 article EN Nuclear Fusion 2008-08-27

The ASDEX Upgrade programme is directed towards physics input to critical elements of the ITER design and preparation operation, as well addressing issues for a future DEMO design. After finalization tungsten coating plasma facing components, re-availability all flywheel-generators allowed high-power operation with up 20 MW heating power at I p 1.2 MA. Implementation alternative ECRH schemes (140 GHz O2- X3-mode) facilitated central above n e = × 10 m −3 low q 95 B t 1.8 T. Central O2-mode...

10.1088/0029-5515/51/9/094012 article EN Nuclear Fusion 2011-08-31

Abstract The pedestal structure, edge transport and linear MHD stability have been analyzed in a series of JET with the ITER-like wall hydrogen (H) deuterium (D) type I ELMy H-mode plasmas. pressure is typically higher D than H at same input power gas rate, difference mainly due to lower density (Maggi et al (JET Contributors) 2018 Plasma Phys. Control. Fusion 60 014045). A balance analysis has shown that inter-ELM separatrix loss required maintain similar top pressure. This qualitatively...

10.1088/1741-4326/abdd77 article EN Nuclear Fusion 2021-01-20

Abstract Sustained operation of high-performance, ITER-baseline scenario plasmas at the high levels input power ( <?CDATA ${\lesssim}40\,\textrm{MW}$?> <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:mo>≲</mml:mo> </mml:mrow> <mml:mn>40</mml:mn> <mml:mtext>MW</mml:mtext> </mml:math> ) required to achieve ∼15 MW D-T fusion in JET-ILW requires careful optimisation fuelling avoid an unacceptable disruption rate due excessive radiation, primarily from...

10.1088/1361-6587/ac1567 article EN cc-by Plasma Physics and Controlled Fusion 2021-07-16
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