D. Bonfiglio
A5041354375- Magnetic confinement fusion research
- Ionosphere and magnetosphere dynamics
- Superconducting Materials and Applications
- Fusion materials and technologies
- Solar and Space Plasma Dynamics
- Plasma Diagnostics and Applications
- Laser-Plasma Interactions and Diagnostics
- Particle accelerators and beam dynamics
- Quantum chaos and dynamical systems
- Physics of Superconductivity and Magnetism
- Geomagnetism and Paleomagnetism Studies
- Characterization and Applications of Magnetic Nanoparticles
- Astro and Planetary Science
- Dust and Plasma Wave Phenomena
- Magnetic Field Sensors Techniques
- Cold Atom Physics and Bose-Einstein Condensates
- Quantum, superfluid, helium dynamics
- Particle Accelerators and Free-Electron Lasers
- Nuclear reactor physics and engineering
- Modular Robots and Swarm Intelligence
- Quantum and electron transport phenomena
- Laser-induced spectroscopy and plasma
- Electrostatic Discharge in Electronics
- Micro and Nano Robotics
- Electrohydrodynamics and Fluid Dynamics
National Agency for New Technologies, Energy and Sustainable Economic Development
2015-2024
University of Padua
2015-2024
Institute for the Science and Technology of Plasmas
2022-2024
Innova (Italy)
2020
Princeton Plasma Physics Laboratory
2011-2013
Princeton University
2013
Los Alamos National Laboratory
2013
Fusion (United States)
2011
Centre National de la Recherche Scientifique
2011
Aix-Marseille Université
2011
JOREK is a massively parallel fully implicit non-linear extended MHD code for realistic tokamak X-point plasmas. It has become widely used versatile studying large-scale plasma instabilities and their control developed in an international community. This article gives comprehensive overview of the physics models implemented, numerical methods applied solving equations studies performed with code. A dedicated section highlights some verification work done hierarchy different available...
Abstract An overview is presented of the progress since 2021 in construction and scientific programme preparation Divertor Tokamak Test (DTT) facility. Licensing for building has been granted at end 2021. Cat. A radiologic source also 2022. The toroidal field magnet system progressing. prototype 170 GHz gyrotron produced it now under test on FALCON design vacuum vessel, poloidal coils civil infrastructures completed. shape first DTT divertor agreed with EUROfusion to different plasma exhaust...
The RFX-mod machine (Sonato et al 2003 Fusion Eng. Des. 66 161) recently achieved, for the first time in a reversed-field pinch, high plasma current up to 1.6 MA with good confinement. Magnetic feedback control of magnetohydrodynamic instabilities was essential reach goal. As is raised, spontaneously accesses new helical state, starting from turbulent multi-helical conditions. Together this raise, ratio between dominant and secondary mode amplitudes increases continuous way. This brings...
RFX-mod is a Reversed Field Pinch device that allowed performing experiments in regimes with plasma current up to 2 MA, thanks its MHD active control system. Experiments have shown improved performances are obtained when the resonant part of m = 1 spectrum one dominant tearing mode much higher than other secondary ones (quasi single helicity states). Tearing modes play crucial role determining energy and particle transport. Based on present understanding interplay between passive conductive...
Abstract Recent studies suggest significant time delay between the Shattered Pellet Injection (SPI) fragment arrival and temperature radiative collapse could exist in ITER, depending on impurity assimilation plasma thermal reservoir. Hence some cases fragments reach core even before edge occurs triggers strong stochastic transport. This be beneficial for heat load mitigation hot-tail runaway electron suppression. To investigate expected radiation, thus magneto-hydrodynamic (MHD) response...
Abstract Precise values for radiated energy in tokamak disruption experiments are needed to validate mitigation techniques burning plasma tokamaks like ITER and SPARC. Control room analysis of power ( P rad ) on JET assumes axisymmetry, since fitting 3D radiation structures with limited bolometry coverage is an under-determined problem. In mitigated disruptions, toroidally asymmetric 3D, due fast-growing MHD modes localized impurity sources. To address this problem, Emis3D adopts a physics...
Abstract The pre-thermal quench (pre-TQ) dynamics of a pure deuterium ( <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msub> <mml:mi mathvariant="normal">D</mml:mi> </mml:mrow> <mml:mn>2</mml:mn> </mml:msub> </mml:math> ) shattered pellet injection (SPI) into <mml:mn>3</mml:mn> <mml:mstyle scriptlevel="0"/> <mml:mi>MA</mml:mi> / <mml:mn>7</mml:mn> <mml:mi>MJ</mml:mi> JET H-mode plasma is studied via 3D non-linear MHD modelling with the JOREK code....
RFX-mod is a reversed field pinch (RFP) experiment equipped with system that actively controls the magnetic boundary. In this paper we describe results of new control algorithm, clean mode (CMC), in which aliasing sideband harmonics generated by discrete saddle coils corrected real time. CMC operation leads to smoother (i.e. more axisymmetric) Tearing modes rotate (up 100 Hz) and partially unlock. Plasma–wall interaction diminishes due decrease non-axisymmetric shift plasma column. With...
We define the safety factor $q$ for helical plasmas of experiment RFX-mod by accounting actual three-dimensional nature magnetic flux surfaces. Such a profile is not monotonic but goes through maximum located in vicinity electron transport barriers measured high resolution Thomson scattering diagnostic. Helical states with single axis obtained viscoresistive magnetohydrodynamic numerical simulations exhibit similar nonmonotonic profiles provided that final are preceded island phase, like experiment.
With the exploration of MA plasma current regime in up to 0.5 s long discharges, RFX-mod has opened new and very promising perspectives for reversed field pinch (RFP) magnetic configuration, made significant progress understanding improving confinement controlling stability. A big leap with respect previous knowledge expectations on RFP physics performance been by since last 2006 IAEA Fusion Energy Conference. self-organized helical equilibrium experimentally achieved (the Single Helical...
We report the first nonlinear three-dimensional magnetohydrodynamic (MHD) numerical simulations of reversed-field pinch (RFP) that exhibit a systematic repetition quasisingle helicity states with same dominant mode in between reconnection events. This distinctive feature experimental self-organized helical RFP plasmas is reproduced MHD at low dissipation by allowing modulation plasma magnetic boundary similar to one. Realistic amplitudes and topology are also found.
JOREK 3D non-linear MagnetoHydroDynamic (MHD) simulations of pure Deuterium Shattered Pellet Injection in ITER are presented. It is shown that such a scheme could allow diluting the plasma by more than factor 10 without immediately triggering large MHD activity, provided background impurity density low enough. This appears as promising strategy to reduce risk hot tail Runaway Electron (RE) generation and avoid RE beams altogether ITER, motivating further studies this direction.
Abstract The RFX-mod2 installation is planned to be completed by 2024 and the start of operations expected in 2025. high flexibility machine (already tested previous RFX-mod experiment) allows operation Reversed Field Pinch tokamak configuration as well ultra-low q pulses. In this work we present predictive analysis on transport, performances plasma control view first experimental campaigns.
Abstract This paper is dealing with the physics basis used for design of Divertor Tokamak Test facility (DTT), under construction in Frascati (DTT 2019 DTT interim report (2019)) Italy, and description main target plasma scenarios device. The goal will be study power exhaust, intended as a fully integrated core-edge problem, eventually to propose an optimized divertor European DEMO plant. approach described their features are reported, by using simulations performed state-of-the-art codes...
Optimization of machine operation, including plasma position control, density control and especially feedback on multiple magnetohydrodynamic modes, has led RFX-mod to operate reliably at 1.5 MA, the highest current ever achieved a reversed field pinch (RFP). At high low magnetic topology spontaneously self-organizes in an Ohmical helical symmetry, with new axis helically twisting around geometrical torus. The separatrix island disappears leaving wide symmetric thermal structure large...
The reversed field pinch configuration is characterized by the presence of magnetic structures both in core and at edge: core, high plasma current spontaneous development a helical structure accompanied appearance internal electron transport barriers; edge strong pressure gradients, identifying an barrier, are observed too, related to position reversal surface.
In the reversed field pinch RFX-mod strong electron temperature gradients develop when Single-Helical-Axis regime is achieved. Gyrokinetic calculations show that in region of microtearing instabilities are dominant turbulent mechanism acting on ion Larmor radius scale. The quasi-linear evaluation thermal conductivity good agreement with experimental estimates.
RFX-mod [Sonato et al., Fusion Eng. Des. 66, 161 (2003)] exploits its 192 active coils in both reversed-field pinch (RFP) and tokamak configurations with varying degrees of 3D shaping, providing also a test bed for validating stellarator codes nonlinear magnetohydrodynamic codes. This makes unique flexible facility comparative studies on shaping control. The paper discusses how fields allow access to RFP advanced regimes. are used feedback control Single Helicity (SH) equilibria 1/7 helicity...
This paper reports the main recent results of RFX-mod fusion science activity.The device is characterized by a unique flexibility in terms accessible magnetic configurations.Axisymmetric and helically shaped Reversed-field pinch equilibria have been studied, along with tokamak plasmas wide range q(a) regimes (spanning from 4 down to 1.2 values).The full configurations between two, so-called ultra low-q ones, has explored, aim studying specific physical issues common all equilibria, such as,...
Nonlinear fluid modelling predictions of qualitatively new self-organized helical states in the reversed-field pinch configuration are confirmed by experiments RFX-mod device. The realized using a seed edge magnetic field, which can impose its pitch to whole plasma. In simulations, we show increased order and reduced transport field lines regimes with twist non-resonant mode. We reveal existence Cantori, encompassing region characterized conserved surfaces, act as barriers lines. This opens...
Stationary 3D equilibria can form in fusion plasmas via saturation of magnetohydrodynamic (MHD) instabilities or stimulated by external fields. In these cases the current profile is anomalously broad due to magnetic flux pumping produced MHD modes. Flux plays an important role hybrid tokamak plasmas, maintaining minimum safety factor above unity and thus removing sawteeth. It also enables steady-state operation, redistributing non-inductive driven near center electron cyclotron waves. A...
The origin of the dynamo velocity field reversed pinch within visco-resistive MHD modeling is uncovered. main component this an electrostatic drift. corresponding related to a small charge separation which consistent with quasineutrality approximation, and should be present in real plasmas, too. While quite natural stationary single helicity state, analysis shown extend also nonstationary multiple regime. Numerical simulations provide spatial distribution fields separation.
The modified RFX is a very flexible device used for variety of control schemes MHD instabilities and advanced reverse field pinch scenarios. Relative to the previous machine, RFX-mod has thin Cu shell with vertical penetration time τS, lowered from 450 50 ms shell/plasma proximity b/a = 1.24–1.1. Toroidal equilibrium feedback-controlled new power supplies provide better B control. Newly designed graphite tiles protect vessel localized deposition. A mesh 192 external saddle coils, supervised...
Within the framework of magnetohydrodynamic (MHD) numerical modeling, reversed field pinch (RFP) has been found to develop turbulent or laminar regimes switching from former latter in a continuous way when strength dissipative forces increases. The solution corresponds simple global helical deformation current channel and is associated with an electrostatic dynamo field. related drift yields main component velocity While quite natural stationary state, this analysis shown extend also dynamic...