A5062988561- Magnetic confinement fusion research
- Particle accelerators and beam dynamics
- Plasma Diagnostics and Applications
- Superconducting Materials and Applications
- Ionosphere and magnetosphere dynamics
- Fusion materials and technologies
- Particle Accelerators and Free-Electron Lasers
- Laser-Plasma Interactions and Diagnostics
- Solar and Space Plasma Dynamics
- Plasma Applications and Diagnostics
- Atomic and Molecular Physics
- Electrohydrodynamics and Fluid Dynamics
- Nuclear reactor physics and engineering
- Gyrotron and Vacuum Electronics Research
- Gas Dynamics and Kinetic Theory
- Silicon and Solar Cell Technologies
- Superconducting and THz Device Technology
- Muon and positron interactions and applications
- Microbial Inactivation Methods
- Catalytic Processes in Materials Science
- Metal and Thin Film Mechanics
- Calibration and Measurement Techniques
- Geomagnetism and Paleomagnetism Studies
- Magnetic properties of thin films
- Inhalation and Respiratory Drug Delivery
National Agency for New Technologies, Energy and Sustainable Economic Development
2015-2024
University of Padua
2014-2024
Fraunhofer Institute for Interfacial Engineering and Biotechnology
2018
John Wiley & Sons (Germany)
2018
University of Bari Aldo Moro
2018
Polytechnique Montréal
2018
Istituto Nazionale di Fisica Nucleare
2015
Institute of Market Economy, Social Policy and Law
2015
University of Milan
2013
Max Planck Society
2004
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 objective of this study was to determine the efficacy and mechanisms inactivation two clinically relevant ESKAPE bacteria namely Pseudomonas aeruginosa methicillin-resistant Staphylococcus aureus by atmospheric pressure cold plasma.Plasma generated between brass grids applying a radiofrequency electric field flow helium. Intracellular generation reactive species, alterations in cell membrane, planktonic or biofilm growth were studied. Results compared with commonly used antimicrobial...
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...
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...
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...
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....
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...
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...
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...
A new bench‐top reactor employing a streamer discharge in air was developed and tested for potential use an advanced oxidation stage water treatment processes. The complex heterogeneous system the ensuing chemical processes were characterized using integrated approach to map morphology of plasma/gas/liquid interface, identify plasma short‐lived excited species, determine oxidants solution monitor organic pollutants degradation. Three model used these experiments, rhodamine B, phenol...
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.
Characteristics of toroidal plasma rotation have been experimentally investigated using charge exchange recombination spectroscopy in the ASDEX Upgrade tokamak. Ion cyclotron resonance frequency (ICRF) heating is found to cause a reduction velocity, V, driven by neutral beam injection (NBI) co- and counter-current directions. The attributed an increasing momentum diffusivity connected with confinement degradation additional ICRF power flux, not induced force related radial non-ambipolar...
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.
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...
Neutral Beam Injectors (NBIs), which need to be strongly optimized in the perspective of DEMO reactor, request a thorough understanding negative ion source used and multi-beamlet optics. A relatively compact radio frequency (rf) source, named NIO1 (Negative Ion Optimization 1), with 9 beam apertures for total H− current 130 mA, 60 kV acceleration voltage, was installed at Consorzio RFX, including high voltage deck an X-ray shield, provide test bench optimizations activities support ITER NBI...
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 ITER project requires additional heating provided by two neutral beam injectors using 40 A negative deuterium ions accelerated at 1 MV. As the requirements have never been experimentally met, a test facility is under construction Consorzio RFX, which hosts experiments: SPIDER, full-size 100 kV ion source prototype, and MITICA, MeV injector prototype. Since diagnostics in will be mainly limited to thermocouples, due neutron gamma radiation access, it crucial thoroughly investigate...