M. Agostini
A5062386074- Magnetic confinement fusion research
- Particle accelerators and beam dynamics
- Plasma Diagnostics and Applications
- Ionosphere and magnetosphere dynamics
- Superconducting Materials and Applications
- Fusion materials and technologies
- Laser-Plasma Interactions and Diagnostics
- Solar and Space Plasma Dynamics
- Particle Accelerators and Free-Electron Lasers
- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Quantum chaos and dynamical systems
- Fluid Dynamics and Turbulent Flows
- Vacuum and Plasma Arcs
- Metal and Thin Film Mechanics
- Physics of Superconductivity and Magnetism
- Atomic and Subatomic Physics Research
- Complex Systems and Time Series Analysis
- Gas Dynamics and Kinetic Theory
- MXene and MAX Phase Materials
- Electrostatic Discharge in Electronics
- Advanced Thermodynamics and Statistical Mechanics
- Aluminum Alloys Composites Properties
- Meteorological Phenomena and Simulations
National Agency for New Technologies, Energy and Sustainable Economic Development
2016-2025
University of Padua
2016-2025
Institute for the Science and Technology of Plasmas
2022-2025
Institut de Recherche sur la Fusion par Confinement Magnétique
2024
CEA Cadarache
2024
University of Rome Tor Vergata
2024
Oak Ridge Associated Universities
2022
National Centre for Nuclear Research
2021
Sapienza University of Rome
2019
Princeton Plasma Physics Laboratory
2016
The ITER Neutral Beam Test Facility (NBTF), called PRIMA (Padova Research on Megavolt Accelerator), is hosted in Padova, Italy and includes two experiments: MITICA, the full-scale prototype of heating neutral beam injector, SPIDER, full-size radio frequency negative-ions source. NBTF realization exploitation SPIDER MITICA have been recognized as necessary to make future operation injectors efficient reliable, fundamental achievement thermonuclear-relevant plasma parameters ITER. This paper...
The ITER project requires additional heating by two neutral beam injectors, each accelerating to 1 MV a 40 A of negative deuterium ions, deliver the plasma power about 17 MW for one hour. As these requirements have never been experimentally met, it was recognized as necessary setup test facility, PRIMA (Padova Research on Megavolt Accelerator), in Italy, including full-size ion source, SPIDER, and prototype whole injector, MITICA, aiming develop injectors be installed ITER. This realization...
Abstract The negative-ion based neutral beam injector for heating and current drive of the ITER plasma (ITER HNB) is under development, at present focusing on optimization full-scale source in SPIDER test stand. production H − or D ions ion low work function surfaces obtained by caesium evaporation. This paper describes conditioning procedure corresponding performances during first operation with caesium. Technical solutions to overcome limitations stand are described. influence parameters...
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...
SARS-CoV-2 induces a spectrum of clinical conditions ranging from asymptomatic infection to life threatening severe disease. Host microRNAs have been involved in the cytokine storm driven by and proposed as candidate biomarkers for COVID-19.
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...
A detailed cross-device investigation on the role of filamentary dynamics in high-density regimes has been performed within EUROfusion framework, comparing ASDEX Upgrade (AUG) and TCV tokamaks. Both devices run density ramp experiments at different levels plasma current, keeping toroidal field or q95 constant order to disentangle parallel connection length current. During scan a field, both scrape-off layer (SOL) profiles tend develop clear SOL shoulder lower edge whenever current is...
Heating neutral beam (HNB) injectors, necessary to achieve burning conditions and control plasma instabilities in ITER, are characterized by such demanding parameters that a test facility (NBTF) dedicated their development optimization is being realized Padua (Italy) with direct contributions from the Italian government (through Consorzio RFX as host entity) ITER international organization (with kind domestic agencies of Europe, Japan India) technical scientific support various European...
The requirements of ITER neutral beam injectors (1 MeV, 40 A negative deuterium ion current for 1 h) have never been simultaneously attained; therefore, a dedicated Neutral Beam Test Facility (NBTF) was set up at Consorzio RFX (Padova, Italy). NBTF includes two experiments: SPIDER (Source the Production Ions Deuterium Extracted from Rf plasma), full-scale prototype source injectors, with 100 keV accelerator, to investigate and optimize properties source; MITICA, entire injector, devoted...
Abstract The impact of plasma shaping on the properties high density H-mode scrape-off layer (SOL) profiles and transport at outer midplane has been investigated Tokamakà configuration variable. experimental dataset acquired by evolving upper triangularity while keeping other parameters constant. scan comprises <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:msub> <mml:mi>δ</mml:mi> <mml:mrow> <mml:mi mathvariant="normal">u</mml:mi>...
Stable operation with control on magnetohydrodynamic modes has been obtained in the modified reversed field experiment employing a set of 192 feedback controlled saddle coils. Improvements plasma temperature, confinement (twofold), and pulse length (threefold) and, as consequence magnetic fluctuation reduction, strong mitigation plasma-wall interaction mode locking are reported.Received 27 January 2006DOI:https://doi.org/10.1103/PhysRevLett.97.075001©2006 American Physical Society
The ITER heating neutral beam (HNB) injector, based on negative ions accelerated at 1 MV, will be tested and optimized in the SPIDER source MITICA full injector prototypes, using a set of diagnostics not available HNB. RF source, where H−/D− production is enhanced by cesium evaporation, monitored with thermocouples, electrostatic probes, optical emission spectroscopy, cavity ring down, laser absorption spectroscopy. analyzed cooling water calorimetry, short pulse instrumented calorimeter,...
SPIDER is one of the two projects ITER Neutral Beam Test Facility (NBTF) under construction in Padova, Italy, at Consorzio RFX premises; it will have a 100 keV beam source with full-size prototype radiofrequency (RF) ion for Injector (NBI), designed to operate pulse length up 3600 s, featuring ITER-like filter field configuration, caesium oven layout and wide set diagnostics.These features allow reproducing operation like as cannot be done any other existing test facility.SPIDER realization...
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...
Giant negative ion sources for neutral beam injectors deliver huge currents, thanks to their multi-beamlet configuration. As the single-beamlet optics defines transmission losses along beamline, extraction of a similar current all beamlets is extremely desirable, in order facilitate source operation (i.e., around perveance match). This Review investigates correlation between vertical profile intensity and profiles plasma properties at region source, focusing on influence increasing cesium...
An overview of the recent operations and main results cesium injection in Source for Production Ions Deuterium Extracted from Rf plasma (SPIDER) negative ion source are described this contribution. In experiments without injection, all SPIDER plants were tested to verify basic expectations on operational parameters (e.g., electron cooling effectiveness magnetic filter field) determine its region. For beam properties, it was shown that current density varies across vertical direction....
The characterization of the spatial distribution particle trajectories, or respective current distribution, in powerful electron beams is an important scientific and practical task necessary to improve quality beam technologies. For various applications, a small divergence required transport over long distances focus it onto spot. Even if one has simultaneous knowledge accelerating voltage, current, coil (or magnetic field), vacuum level overall, they provide little insight into properties...
We present an overview of FTU experiments on runaway electron (RE) generation and control carried out through a comprehensive set real-time (RT) diagnostics/control systems newly installed RE diagnostics. An imaging spectrometer system detects visible infrared synchrotron radiation. A Cherenkov probe measures escaping the plasma. gamma camera provides hard x-ray radial profiles from bremsstrahlung interactions in Experiments onset suppression show that threshold electric field for is larger...
Within the EUROfusion MST1 work package, a series of experiments has been conducted on AUG and TCV devices to disentangle role plasma fueling shape for onset small ELM regimes. On both devices, regimes with high confinement are achieved if only two conditions fulfilled at same time. Firstly, density separatrix must be large enough (), leading pressure profile flattening separatrix, which stabilizes type-I ELMs. Secondly, magnetic configuration close double null (DN), reduction shear in...
Neutral beam injection is one of the most important methods plasma heating in thermonuclear fusion experiments, allowing attainment conditions as well driving current. beams are generally produced by electrostatically accelerating ions, which neutralised before into magnetised plasma. At particle energy required for advanced devices and particularly ITER, neutralisation positive ions very inefficient so that negative used. The present paper devoted to description phenomena occurring when a...
Integrating the plasma core performance with an edge and scrape-off layer (SOL) that leads to tolerable heat particle loads on wall is a major challenge. The new European medium size tokamak task force (EU-MST) coordinates research ASDEX Upgrade (AUG), MAST TCV. This multi-machine approach within EU-MST, covering wide parameter range, instrumental progress in field, as ITER DEMO core/pedestal SOL parameters are not achievable simultaneously present day devices. A two prong adopted. On one...
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...