S. Dal Bello
A5017155565- Magnetic confinement fusion research
- Particle accelerators and beam dynamics
- Superconducting Materials and Applications
- Fusion materials and technologies
- Plasma Diagnostics and Applications
- Ionosphere and magnetosphere dynamics
- Particle Accelerators and Free-Electron Lasers
- Solar and Space Plasma Dynamics
- Laser-Plasma Interactions and Diagnostics
- Power Line Inspection Robots
- Atomic and Molecular Physics
- Radiation Effects in Electronics
- Ion-surface interactions and analysis
- Metal and Thin Film Mechanics
- Electromagnetic Launch and Propulsion Technology
- Quantum chaos and dynamical systems
- Geophysical Methods and Applications
- Advanced MEMS and NEMS Technologies
- Diamond and Carbon-based Materials Research
- Nuclear Engineering Thermal-Hydraulics
- Gyrotron and Vacuum Electronics Research
- Spacecraft and Cryogenic Technologies
- Nuclear Physics and Applications
- Muon and positron interactions and applications
- Nuclear Materials and Properties
National Agency for New Technologies, Energy and Sustainable Economic Development
2011-2023
University of Padua
1998-2023
University of Milan
2013
Hendrix College
1999
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...
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 ITER is of key importance in the European fusion roadmap as it aims to prove scientific and technological feasibility a future energy source. The EUROfusion consortium labs within Europe contributing preparation exploitation operation aspires exploit outcomes view DEMO. paper provides an overview major progress obtained recently, carried out frame new (initiated 2021) work-package called ‘ Pr eparation I TER O peration’ (PrIO). directly supported by eleven PrIO contributions given...
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...
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...
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...
An improvement for the vacuum system of multidriver radio frequency (RF) prototype negative ion source SPIDER has been developed, to allow operating at high RF power, while minimizing breakdown probability on outside plasma source. A first-of-its-kind large nonevaporable getter (NEG) pump, based a modular design 384 cartridges totaling about 350 kg ZAO® alloy (composed by Zr-Ti-V-Al) with an installed pumping speed room temperature 330 m3/s hydrogen, will complement existing system, eight...
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.
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,...
The Divertor Tokamak Test facility (DTT) will be a new experimental located at Frascati, Rome, Italy, whose main goal to have better understanding on hot plasma interactions with plasma-facing components (PFCs) and aid in the development of ITER successively DEMO. improved conceptual design beamline for DTT neutral beam heating (NBH) system is here overviewed, particular focus technical solutions adopted fulfill requirements maximize performances. proposed features providing deuterium...
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...
The full three-dimensional (3D) approach is now becoming an important issue for all magnetic confinement configurations. It a necessary condition the stellarator but also tokamak and reversed field pinch (RFP) cannot be completely described in axisymmetric framework. For RFP observation of self-sustained helical configurations with improved plasma performances require better description order to assess new view on this configuration. In framework configuration studies RFX-mod have been...
Reversed field pinches (RFPs) share with tokamaks and stellarators the experimental evidence of an upper limit for maximum value electron density at which they can operate. Above a certain level, well described by Greenwald law RFPs, radiative collapse strong plasma cooling is observed, predominantly due to processes occurring boundary. In RFX-mod RFP close radiating belt, poloidally symmetric toroidally localized, develops in region where shrunk as effect m = 0 tearing modes. The...