A5016103851- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Plasma Diagnostics and Applications
- Ionosphere and magnetosphere dynamics
- HVDC Systems and Fault Protection
- Fusion materials and technologies
- Advanced DC-DC Converters
- Electromagnetic Launch and Propulsion Technology
- Silicon Carbide Semiconductor Technologies
- Physics of Superconductivity and Magnetism
- Ear and Head Tumors
- Particle Accelerators and Free-Electron Lasers
- Facial Nerve Paralysis Treatment and Research
- Head and Neck Cancer Studies
- Salivary Gland Tumors Diagnosis and Treatment
- Multilevel Inverters and Converters
- Electrostatic Discharge in Electronics
- Ear Surgery and Otitis Media
- Nuclear reactor physics and engineering
- Gyrotron and Vacuum Electronics Research
- Oral and Maxillofacial Pathology
- Solar and Space Plasma Dynamics
- Magnetic Field Sensors Techniques
- Head and Neck Surgical Oncology
National Agency for New Technologies, Energy and Sustainable Economic Development
2015-2024
University of Padua
2014-2023
Institute for the Science and Technology of Plasmas
2022-2023
Hospital Universitário de Brasília
2013
Universidade de Brasília
2013
KTH Royal Institute of Technology
2008-2009
Consorzio Venezia Ricerche
2009
University of Verona
2009
Ospedale Castelfranco Veneto
2007-2008
Forschungszentrum Jülich
2008
This paper describes the status of pre-conceptual design activities in Europe to advance technical basis a DEMOnstration Fusion Power Plant (DEMO) come operation around middle this century with main aims demonstrating production few hundred MWs net electricity, feasibility closed-tritium fuel cycle, and maintenance systems capable achieving adequate plant availability. is expected benefit as much possible from ITER experience, terms design, licensing, construction. Emphasis on an integrated...
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...
This paper presents the development and testing of prototype a hybrid mechanical-static dc circuit breaker (CB) for quench protection superconducting magnets based on mechanical switch paralleled to static CB. In normal operation, is closed it handles continuous flow current, minimizing on-state losses. case intervention, opens, commutating current into CB that quickly interrupts transfers discharge resistor, withstanding reapplied voltage. was carried out face solve some issues this design...
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...
The DEMO reactor is expected to be the first application of fusion for electricity generation in near future. To this aim, conceptual design activities are progressing Europe (EU) under lead EUROfusion Consortium order drive on development major tokamak systems. In 2014, carried out by magnet system project team were focused toroidal field (TF) and demonstrated achievements terms concept proposals consolidated evaluations against criteria. Several R&D conducted parallel, together with broad...
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...
The European DEMO, i.e. the demonstration fusion power plant designed in framework of Roadmap to Fusion Electricity by EUROfusion Consortium, is approaching end pre-conceptual design phase, be accomplished with a Gate Review 2020, which all DEMO subsystems will reviewed panels independent experts. latest 2018 baseline has major and minor radius 9.1 m 2.9 m, plasma current 17.9 MA, toroidal field on axis 5.2 T, peak toroidal-field (TF) conductor 12.0 T. 900 ton heavy TF coil prepared four...
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 EU DEMO Plant Electrical System (PES) main scopes are to supply all the plant electrical loads and deliver Power Transmission Grid (PTG) net power generated. studies on PES during Pre-Concept Design (PCD) Phase were mainly addressed understand possible issues, related special features both of generated, with respect a same size, be supplied loads. For this purpose, approach was start design different components adopting technologies already utilized in fusion experiments Nuclear Plants...
Abstract: Nowadays, facial paralysis is an uncommon complication of acute inflammation the middle ear, with estimated incidence 0.005%; it was not so rare in pre‐antibiotic era, occurring 0.5−0.7% ear inflammatory processes. We would like to highlight this otitis media, a common paediatric complaint. present three new cases palsy children media and discuss etiological mechanisms different approaches treatment; flow chart for also presented. Our patients recovered completely after...
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...
The Plant Electrical System (PES) of the European DEMOnstration fusion power plant (DEMO), presently under conceptual design, shall supply to loads and deliver net Power Transmission Grid (PTG). Starting from available requirements, applicability DEMO PES technologies design approaches adopted in ITER nuclear plants (NPP) has been evaluated. This article presents results survey proposes alternative solutions deal with identified criticalities.
A hysteresis control method for three-phase, current-controlled, VSI PWM (pulse width modulation) inverters characterized by constant switching frequency is presented. The based on substantial improvement of the principle minimization interference among modulations various phases, which does not require any knowledge load parameters or EMF, provided symmetric. Interference allows PLL (phase-locked loop) frequency. inherent benefits proposed technique are full exploitation inverter voltage...
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.