M. Fontana

ORCID: 0000-0002-7979-7483
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About
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Research Areas
  • Magnetic confinement fusion research
  • Fusion materials and technologies
  • Ionosphere and magnetosphere dynamics
  • Superconducting Materials and Applications
  • Plasma Diagnostics and Applications
  • Particle accelerators and beam dynamics
  • Laser-Plasma Interactions and Diagnostics
  • Nuclear reactor physics and engineering
  • Atomic and Subatomic Physics Research
  • Dust and Plasma Wave Phenomena
  • Anomaly Detection Techniques and Applications
  • Solar and Space Plasma Dynamics
  • Wireless Sensor Networks and IoT
  • Geomagnetism and Paleomagnetism Studies
  • Nuclear Physics and Applications
  • Time Series Analysis and Forecasting
  • Radiation Detection and Scintillator Technologies
  • Geophysics and Gravity Measurements
  • Quantum Chromodynamics and Particle Interactions
  • Calibration and Measurement Techniques
  • Viral Infections and Vectors
  • Advanced Sensor and Control Systems
  • Optical and Acousto-Optic Technologies
  • Precipitation Measurement and Analysis
  • Nuclear Materials and Properties

École Polytechnique Fédérale de Lausanne
2016-2025

Culham Science Centre
2022-2024

United Kingdom Atomic Energy Authority
2023-2024

Culham Centre for Fusion Energy
2023-2024

National Agency for New Technologies, Energy and Sustainable Economic Development
2022

National Centre for Nuclear Research
2021

Fundación Ciencias Exactas y Naturales
2018

Consejo Nacional de Investigaciones Científicas y Técnicas
2018

University of Buenos Aires
2018

CentraleSupélec
2000

The negative triangularity tokamak (NTT) is a unique reactor concept based on 'power-handling-first' philosophy with the heat exhaust problem as leading concern. present paper exposes using L-mode edge NTT configuration, providing merits of no (or very weak) edge-localized modes, larger particle flux and large major radius for power handling. It shown that reasonably compact (Rp from 9 m to 7 m) possible by achieving higher confinement improvement (HH = 1.5) and/or utilizing magnetic field...

10.1088/1741-4326/ab076d article EN Nuclear Fusion 2019-02-15

Abstract The tokamak à configuration variable (TCV) continues to leverage its unique shaping capabilities, flexible heating systems and modern control system address critical issues in preparation for ITER a fusion power plant. For the 2019–20 campaign configurational flexibility has been enhanced with installation of removable divertor gas baffles, diagnostic capabilities an extensive set upgrades new dual frequency gyrotrons. baffles reduce coupling between main chamber allow detailed...

10.1088/1741-4326/ac369b article EN cc-by Nuclear Fusion 2022-03-01

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

Abstract ST40 is a compact, high-field ( <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msub> <mml:mi>B</mml:mi> <mml:mi mathvariant="normal">T</mml:mi> <mml:mn>0</mml:mn> </mml:mrow> </mml:msub> <mml:mtext>⩽</mml:mtext> <mml:mn>2.1</mml:mn> <mml:mstyle scriptlevel="0"/> <mml:mtext>T</mml:mtext> </mml:math> ) spherical tokamak (ST) with mission to expand the physics and technology basis for ST route commercial fusion. The research programme covers...

10.1088/1741-4326/ad6ba7 article EN cc-by Nuclear Fusion 2024-08-06

The TCV tokamak is augmenting its unique historical capabilities (strong shaping, strong electron heating) with ion heating, additional heating compatible high densities, and variable divertor geometry, in a multifaceted upgrade program designed to broaden operational range without sacrificing fundamental flexibility. rooted three-pronged approach aimed at ITER support, explorations towards DEMO, research. A 1 MW, tangential neutral beam injector (NBI) was recently installed promptly...

10.1088/1741-4326/aa6412 article EN cc-by Nuclear Fusion 2017-06-23

The effects of plasma shaping, in particular triangularity (δ), on temperature fluctuations the tokamak à configuration variable have been studied using correlation electron cyclotron emission system. It has found that, ohmic discharges with comparable density profiles, relative fluctuation level measured at edge is significantly reduced plasmas negative respect to positive ones. Additionally, critical gradients for onset turbulence are observed increase plasmas. An estimation length...

10.1088/1741-4326/aa98f4 article EN Nuclear Fusion 2017-11-08

Abstract The research program of the TCV tokamak ranges from conventional to advanced-tokamak scenarios and alternative divertor configurations, exploratory plasmas driven by theoretical insight, exploiting device’s unique shaping capabilities. Disruption avoidance real-time locked mode prevention or unlocking with electron-cyclotron resonance heating (ECRH) was thoroughly documented, using magnetic radiation triggers. Runaway generation high- Z noble-gas injection runaway dissipation...

10.1088/1741-4326/ab25cb article EN cc-by Nuclear Fusion 2019-05-30

Abstract We present an overview of results from a series L–H transition experiments undertaken at JET since the installation ITER-like-wall (JET-ILW), with beryllium wall tiles and tungsten divertor. Tritium, helium deuterium plasmas have been investigated. Initial in tritium show ohmic transitions low density power threshold for ( P LH ) is lower than ones densities, while we still lack contrasted data to provide scaling high densities. In there notable shift which minimum <?CDATA...

10.1088/1741-4326/ac4ed8 article EN Nuclear Fusion 2022-01-25

Abstract The recent deuterium–tritium campaign in JET-ILW (DTE2) has provided a unique opportunity to study the isotope dependence of L-H power threshold an ITER-like wall environment (Be and W divertor). Here we present results from dedicated transition experiments at JET-ILW, documenting tritium plasmas, comparing them with matching deuterium hydrogen datasets. From earlier it is known that as plasma isotopic composition changes deuterium, through varying deuterium/hydrogen concentrations,...

10.1088/1741-4326/acee12 article EN cc-by Nuclear Fusion 2023-10-12

Abstract This paper reports the first experiment carried out in deuterium–tritium addressing integration of a radiative divertor for heat-load control with good confinement. Neon seeding was time D–T plasma as part second campaign JET its Be/W wall environment. The technical difficulties linked to re-ionisation heat load are reported T and D–T. compares impact neon on plasmas their D counterpart detachment, localisation radiation, scrape-off profiles, pedestal structure, edge localised modes global

10.1088/1741-4326/ad69a2 article EN cc-by Nuclear Fusion 2024-07-31

Routine reaction to approaching disruptions in tokamaks is currently largely limited machine protection by mitigating an ongoing disruption, which remains a basic requirement for ITER and DEMO [1]. Nevertheless, mitigated disruption still generates stress the device. Additionally, future fusion devices, high-performance discharge time itself will be very valuable. Instead of reacting only on generic features, occurring shortly before ultimate goal actively avoid at early stage, sustain...

10.1088/1361-6587/aa8d05 article EN Plasma Physics and Controlled Fusion 2017-09-15

JET’s frequency-modulated continuous wave (FMCW) reflectometers have been operating well with the current design since 2005, and density profiles automatically calculated intershot then. However, had long suffered from several shortcomings: poor agreement other diagnostics, sometimes inappropriately moving radially by centimeters, elevated levels of radial jitter, persistent wriggles (strong unphysical oscillations). In this research, techniques are applied to reflectometry data analysis,...

10.1063/5.0176696 article EN Review of Scientific Instruments 2024-04-01

Local gyrokinetic simulations with the GENE code are used to investigate turbulent transport for different levels of neutral beam injection heating power in Tokamak à Configuration Variable (TCV) plasmas both positive and negative edge triangularity. The sensitivity heat fluxes respect main plasma parameters, including background gradients, impurity content, electron temperature, is systematically studied. experimentally measured recovered variations profiles compatible experimental error...

10.1063/1.5115390 article EN Physics of Plasmas 2019-10-01

Abstract The required heating power, <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msub> <mml:mi>P</mml:mi> <mml:mi>LH</mml:mi> </mml:mrow> </mml:msub> </mml:math> , to access the high confinement regime (H-mode) in tritium containing plasmas is investigated JET with ITER-like wall at a toroidal magnetic field of <mml:mi>B</mml:mi> <mml:mi>t</mml:mi> <mml:mo>=</mml:mo> <mml:mn>1.8</mml:mn> T and plasma current <mml:mi>I</mml:mi>...

10.1088/1361-6587/acc423 article EN cc-by Plasma Physics and Controlled Fusion 2023-03-15

Beam-target reactions are responsible for a substantial fraction of the fusion power generated in D-T plasmas JET-ILW (Be/W-wall), with ion temperatures 10-12keV and large neutral-beam injection (NBI) power.It is known that injecting D beam ions energies ~100-150keV T-rich has larger potential beam-target than 50:50 D:T plasmas, but such scenario was never developed past experiments performed JET-C (Carbon-wall) TFTR 90's.On top intrinsic advantages using beams neutron production,...

10.1063/5.0162554 article EN AIP conference proceedings 2023-01-01

The effects of negative triangularity (δ) on confinement and fluctuations in plasmas covering a large range parameters were investigated the tokamak à configuration variable (TCV).The conditions explored this paper include discharges where neutral beam (NB) heating was employed to obtain an electron-ion temperature ratio Te/T i ∼ 1 across fraction plasma profile.This significantly extended δ studied TCV towards more relevant future reactor-like tokamaks.Negative found improve over full...

10.1088/1741-4326/ab4d75 article EN Nuclear Fusion 2019-10-16

The correlation electron cyclotron emission diagnostic of tokamak à configuration variable has recently been upgraded. It now the choice three lines sight: two horizontal placed on low field side vessel, perpendicular to magnetic field, and a dual-axis steerable antenna. polarization radiation collected by latter can be rotated using universal polarizer situated in transmission line. This line is also shared with reflectometry system, allowing simultaneous measurements temperature density...

10.1063/1.4997075 article EN Review of Scientific Instruments 2017-08-01

Axisymmetric (n = 0) density fluctuations measured in the TCV tokamak are observed to possess a frequency f0 which is either varying (radially dispersive oscillations) or constant over large fraction of plasma minor radius global as reported companion paper (Z Huang et al, this issue). Given that scales with sound speed and given poloidal structure fluctuations, these oscillations were interpreted Geodesic Acoustic Modes, even though fact smaller than local linear GAM . In work we employ...

10.1088/1361-6587/aaa2dc article EN Plasma Physics and Controlled Fusion 2017-12-19

This paper provides a comprehensive study of neutron calibration methodologies, specifically highlighting the capabilities for n–γ discrimination in diamond and EJ-309, stilbene scintillation detectors. The process detailed this includes pulse height analysis shape discrimination, relying on charge deposition resulting from both γ interactions. Utilizing 60Co 252Cf radiation sources, energy spectra these sources are obtained. characterized detectors were used ST40 experiments allowed...

10.1063/5.0218866 article EN Review of Scientific Instruments 2024-08-01

Electron-scale micro-turbulence driven by the electron temperature gradient (ETG) instability have recently been shown to impact heat transport in tokamaks.Given relevance of these mechanisms for ITER scenarios, a new study has carried out on TCV tokamak at Swiss Plasma Center, which is equipped with both ECH and NBI heating, allowing investigate ETG transport.Dedicated L-mode discharges performed experimental measurements compared gyrokinetic simulations.The results indicate that ETGs...

10.1088/1741-4326/ab3de4 article EN Nuclear Fusion 2019-08-22

The fully non-inductive sustainment of high normalized beta plasmas (β N ) is a crucial challenge for the steady-state operation tokamak reactor.In order to assess diculties facing such scenarios, regimes have been explored on Tokamak à Conguration Variable (TCV) using newly available 1 MW Neutral Beam Injection (NBI) system.The operating space extended towards that are closer those expected in JT-60SA and ITER, i.e. with signicant NBI Electron Cyclotron Resonance Heating Current Drive...

10.1088/1741-4326/ab2bb6 article EN Nuclear Fusion 2019-06-21

A parametric study of the magnetic dipole behavior in resistive incompressible MHD inside a rotating sphere is performed, using direct numerical simulations and considering Reynolds Ekman numbers as controlling parameters. The tendency to obtain geodynamo-like reversal regimes for sufficiently small large numbers. typical latitude obtained regime around 40 degrees (with respect rotation axis sphere). statistical analysis waiting times between reversals also obtaining non-Poissonian...

10.1103/physrevfluids.3.123702 article EN Physical Review Fluids 2018-12-19
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