M. Sertoli
A5019064515- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Ionosphere and magnetosphere dynamics
- Laser-Plasma Interactions and Diagnostics
- Nuclear reactor physics and engineering
- Particle accelerators and beam dynamics
- Plasma Diagnostics and Applications
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- High-Energy Particle Collisions Research
- Solar and Space Plasma Dynamics
- Radiation Detection and Scintillator Technologies
- Electrostatic Discharge in Electronics
- Particle Detector Development and Performance
- Radiation Effects in Electronics
- Power System Optimization and Stability
- Atomic and Molecular Physics
- Physics of Superconductivity and Magnetism
- Anomaly Detection Techniques and Applications
- Dust and Plasma Wave Phenomena
- Fault Detection and Control Systems
- GNSS positioning and interference
- Laser-induced spectroscopy and plasma
- Metallurgical Processes and Thermodynamics
Tokamak Energy (United Kingdom)
2022-2024
Culham Centre for Fusion Energy
2020-2024
United Kingdom Atomic Energy Authority
2020-2024
Culham Science Centre
2017-2024
Max Planck Institute for Plasma Physics
2012-2022
National Centre of Scientific Research "Demokritos"
2021
Royal Military Academy
2020
Max Planck Society
2010-2019
General Atomics (United States)
2018
CEA Cadarache
2018
A future fusion reactor is expected to have all-metal plasma facing materials (PFMs) ensure low erosion rates, tritium retention and stability against high neutron fluences. As a consequence, intrinsic radiation losses in the edge divertor are comparison devices with carbon PFMs. To avoid localized overheating divertor, low-Z medium-Z impurities be inserted into convert major part of power flux facilitate partial detachment. For burning conditions ITER, which operates not far above L–H...
Abstract Ion temperatures of over 100 million degrees Kelvin (8.6 keV) have been produced in the ST40 compact high-field spherical tokamak (ST). excess 5 keV not previously reached any ST and only obtained much larger devices with substantially more plasma heating power. The corresponding fusion triple product is calculated to be <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msub> <mml:mi>n</mml:mi> <mml:mi>i</mml:mi> <mml:mn>0</mml:mn>...
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...
The W-transport in the core plasma of JET is investigated experimentally by deriving W-concentration profiles from modelling signals soft x-ray cameras. For case pure neutral beam heating W accumulates (r/a < 0.3) approaching W-concentrations 10−3 between sawtooth crashes, which flatten W-profile to a concentration about 3 × 10−5. When central Ion cyclotron resonant additionally applied decays phases that exhibit changed mode activity, while also electron temperature increases and density...
The new full-metal ITER-like wall (ILW) at JET was found to have a profound impact on the physics of disruptions. main difference is significantly lower fraction (by up factor 5) energy radiated during disruption process, yielding higher plasma temperatures after thermal quench and thus longer current times. Thus, larger total conducted resulting in heat loads. Active mitigation by means massive gas injection became necessity avoid beryllium melting already moderate levels magnetic (i.e....
In the recent JET experimental campaigns with new ITER-like wall (JET-ILW), major progress has been achieved in characterization and operation of H-mode regime metallic environments: (i) plasma breakdown at first attempt X-point L-mode recovered a few days operation; (ii) stationary stable type-I ELMy H-modes βN ∼ 1.4 have low high triangularity shape plasmas are showing that their operational domain H = 1 is significantly reduced JET-ILW mainly because need to inject large amount gas (above...
The evolution of the JET high performance hybrid scenario, including central accumulation tungsten (W) impurity, is reproduced with predictive multi-channel integrated modelling over multiple confinement times using first-principle based core transport models.8 channels ( , ) are modelled predictively, self-consistent sources, radiation and magnetic equilibrium, yielding a system non-linearities: This can reproduce observed radiative temperature collapse after several times.W transported...
New H-mode regimes with high confinement, low core impurity accumulation, and small edge-localized mode perturbations have been obtained in magnetically confined plasmas at the Joint European Torus tokamak. Such are achieved by means of optimized particle fueling conditions input power, current, magnetic field, which lead to a self-organized state strong increase rotation ion temperature decrease edge density. An interplay between plasma regions leads reduced turbulence levels outward...
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...
To consolidate International Thermonuclear Experimental Reactor (ITER) design choices and prepare for its operation, Joint European Torus (JET) has implemented ITER's plasma facing materials, namely, Be the main wall W in divertor. In addition, protection systems, diagnostics, vertical stability control were upgraded heating capability of neutral beams was increased to over 30 MW. First results confirm expected benefits limitations all metal components (PFCs) but also yield understanding...
To study the impact of strong impurity radiation on energy confinement and discharge stability at JET-ILW, dedicated high-density, highly heated experiments with neon seeding have been performed. In these an increase in core especially pedestal region plus a characteristic X-point radiator inside confined observed. The increased separatrix had no confinement. Only highest puff rates heating powers () weak H-mode without back-transitions to L-mode (M-mode) could be achieved, while lower or...
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...
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,...
In this paper, the turbulent transport properties of ST40 hot ion plasmas are examined and fully predictive time evolving modelling a plasma pulse was performed. Understanding on spherical tokamaks (STs) is challenging due to their unique geometry characteristics. typically unstable scale Trapped Electron Modes (TEMs) Ubiquitous (UMs), driven from kinetic response trapped particles passing ions, electron Temperature Gradient (ETGs) at edge plasma. A comparison between linear modes...
The transport of argon as trace impurity has been investigated in electron cyclotron resonance heated L-mode discharges at ASDEX Upgrade to test recent theories predicting the rise an outward convection.The profiles coefficients for r/a < 0.65 have determined by analysing linear flux-gradient dependency total ion density evolution after puff.A new methodology experimentally obtain from integrated use two spectroscopic diagnostic and 1D code STRAHL developed.Results confirm enhancement...
A comparison of the impact additional central electron cyclotron resonance heating (ECRH) and ion (ICRH) on behaviour tungsten (W) density in core H-mode plasmas heated with neutral beam injection (NBI) is performed ASDEX Upgrade.Both localized broad profiles power ECRH have been obtained, where reproduce profile shape ICRH density, which applied a hydrogen minority scheme.In contrast to ECRH, produces direct only, eventually heats both electrons ions almost equal fractions.It found that RF...
Abstract Previous studies with first-principle-based integrated modelling suggested that electron temperature gradient (ETG) turbulence may lead to an anti-gyroBohm isotope scaling in JET high-performance hybrid H-mode scenarios. A dedicated comparison study against higher-fidelity invalidates this claim. Ion-scale magnetic field perturbations included, can match the power balance fluxes within error margins. Multiscale gyrokinetic simulations from two distinct codes produce no significant...
The lithium beam diagnostic at ASDEX Upgrade routinely delivers electron density profiles in the plasma edge by impact excitation spectroscopy. An accurate background subtraction requires a periodically chopped beam. A new, improved chopping system was developed and installed. It involves voltage modulation for extractor electrode deflection plates. of reduces unused portion ions improves stability with respect to its position. Furthermore, data indicate an extended emitter lifetime. also...
This paper covers aspects of long-term evolution intrinsic impurities in the JET tokamak with respect to newly installed ITER-like wall (ILW). At first changes related change over from JET-C JET-ILW beryllium (Be) as main material and tungsten (W) divertor are discussed. The impurity fluxes W studying migration is described. In addition, a statistical analysis transient events causing significant plasma contamination radiation losses shown. findings comprise drop carbon content (×20) (see...
Recent studies dedicated to the characterisation of in-vessel dust in JET with new ITER-like wall (ILW) show that levels are orders magnitude lower compared latter stages carbon-wall (CW) period and decreasing operational time. Less than 1 g was recovered a recent inspection, more 200 material at end JET-CW life. inspection ILW shows low rates re-deposition only small areas damage type likely create particulate matter. Quantifiers from laser scattering techniques also indicate an order...
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....
A new method for the determination of 2D intrinsic tungsten density profiles in presence saturated MHD instabilities at ASDEX Upgrade is presented.For first time full decoupling impurity from electron and temperature contributions to experimental SXR tomographic reconstructions can be performed.The analysis relies on a combination tomography with reconstruction through harmonic decomposition 1D ECE temperature.The applicable any magnetic perturbation as long poloidal toroidal mode numbers m...