A. Rizzolo
A5037464573- Particle accelerators and beam dynamics
- Magnetic confinement fusion research
- Plasma Diagnostics and Applications
- Superconducting Materials and Applications
- Particle Accelerators and Free-Electron Lasers
- Fusion materials and technologies
- Atomic and Molecular Physics
- Metal and Thin Film Mechanics
- Magnetic Field Sensors Techniques
- Electrical and Thermal Properties of Materials
- Electrostatic Discharge in Electronics
- Metallurgical Processes and Thermodynamics
- Nuclear reactor physics and engineering
- Silicon and Solar Cell Technologies
- Magneto-Optical Properties and Applications
- Advanced Sensor Technologies Research
- Advanced MEMS and NEMS Technologies
- Semiconductor materials and devices
- Nuclear and radioactivity studies
- Laser-Plasma Interactions and Diagnostics
- Ionosphere and magnetosphere dynamics
- Mass Spectrometry Techniques and Applications
- Nuclear Physics and Applications
National Agency for New Technologies, Energy and Sustainable Economic Development
2013-2024
University of Padua
2015-2023
University of Milan
2013
Japan Atomic Energy Agency
2012
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...
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 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...
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...
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....
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 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...
This paper summarizes the main achievements of RFX fusion science program in period between 2008 and 2010 IAEA Fusion Energy Conferences. RFX-mod is largest reversed field pinch world, equipped with a system 192 coils for active control MHD stability. The discovery understanding helical states electron internal transport barriers core temperature >1.5 keV significantly advances perspectives configuration. Optimized experiments plasma current up to 1.8 MA have been realized, confirming...
The megavolt ITER injector and concept advancement experiment is the prototype test bed of heating current drive neutral beam injectors, currently in final design phase, view installation Padova Research on Injector Megavolt Accelerated facility Padova, Italy. source key component system, as its goal generation 1 MeV accelerated deuterium or hydrogen negative ions. This paper presents highlights latest developments for finalization MITICA design, together with a description most recent...
The RFX-mod device is operated both as a reversed field pinch (RFP), where advanced regimes featuring helical shape develop, and tokamak. Due to its flexibility, contributing the solution of key issues in roadmap ITER DEMO, including MHD instability control, internal transport barriers, edge turbulence, isotopic effect, high density limit three-dimensional (3D) non-linear modelling. This paper reports recent advancements understanding self-organized states, strong electron barrier, RFP...