A5067589942- Particle accelerators and beam dynamics
- Magnetic confinement fusion research
- Plasma Diagnostics and Applications
- Particle Accelerators and Free-Electron Lasers
- Vacuum and Plasma Arcs
- Superconducting Materials and Applications
- Electrostatic Discharge in Electronics
- Fusion materials and technologies
- High voltage insulation and dielectric phenomena
- Nuclear Physics and Applications
- Particle Detector Development and Performance
- Lightning and Electromagnetic Phenomena
- Semiconductor materials and devices
- Power Transformer Diagnostics and Insulation
- Metal and Thin Film Mechanics
- Atomic and Molecular Physics
- Muon and positron interactions and applications
- Gyrotron and Vacuum Electronics Research
- Silicon Carbide Semiconductor Technologies
- Advanced ceramic materials synthesis
- Electrical Fault Detection and Protection
- Ionosphere and magnetosphere dynamics
- Ion-surface interactions and analysis
- Advanced X-ray and CT Imaging
- Electron and X-Ray Spectroscopy Techniques
National Agency for New Technologies, Energy and Sustainable Economic Development
2015-2024
University of Padua
2009-2024
Institute for the Science and Technology of Plasmas
2022
European Society for Organ Transplantation
2014
University of Milan
2013
Japan Atomic Energy Agency
2012
Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Legnaro
2009-2011
Université Toulouse III - Paul Sabatier
2009
Centre National de la Recherche Scientifique
2009
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2009
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 ITER Neutral Beam Test Facility (PRIMA) is presently under construction at Consorzio RFX (Padova, Italy). PRIMA includes two experimental devices: an ITER-size ion source with low voltage extraction, called SPIDER, and the full prototype of whole Heating Beams (HNBs), MITICA. purpose MITICA to demonstrate that all operational parameters HNB accelerator can be experimentally achieved, thus establishing a large step forward in performances neutral beam injectors comparison present...
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...
The ITER Neutral Beam Test Facility (PRIMA) is planned to be built at Consorzio RFX (Padova, Italy). PRIMA includes two experimental devices: a full size ion source with low voltage extraction called SPIDER and neutral beam injector power MITICA. the first device operated, aiming testing of negative (made H − in later stage D ions) from an source. main requirements this experiment are /D extracted current density larger than 355/285 A m −2 , energy 100 keV pulse duration up 3600 s. Several...
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 physics design of the accelerator for heating neutral beamline on ITER is now finished and this paper describes considerations choices which constitute basis design. Equal acceleration gaps 88 mm have been chosen to improve voltage holding capability while keeping beam divergence low. Kerbs (metallic plates around groups apertures, attached downstream surface grids) are used compensate beamlet–beamlet interaction point beamlets in right direction. A novel magnetic configuration...
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...
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....
Two Neutral Beam Injectors (NBI) are foreseen to provide a substantial fraction of the heating power necessary ignite thermonuclear fusion reactions in ITER. The development NBI system at unprecedented parameters (40 A negative ion current accelerated up 1 MV) requires realization full scale prototype, be tested and optimized Test Facility under construction Padova (Italy). beam source is key component design multi-grid accelerator goal multi-national collaborative effort. In particular,...
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 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 voltage holding in the 1 MV ITER Neutral Beam Accelerator is recognized to be one of most critical issues for long lasting beam operation, due complex electrostatic structure formed by differently shaped electrodes polarized at different potentials. At present, no model available predict breakdown probability system with a comparable complexity degree. This paper aimed proposing an innovative modelling prediction such systems, based on implementation micro particle (clump) induced...
In the framework of program for construction—in Padova, Italy—of first prototype International Thermonuclear Experimental Reactor 1 MeV–16 MW negative neutral beam injector (NNBI), an R&D activity on voltage holding in vacuum has been initiated since 2009, aimed at supporting design, construction, and development NNBI accelerator. For this purpose, high-voltage Padova test facility, designed to operate up 800 kV, built, parallel a multivoltage multielectrode prediction model (VHPM). This...
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...
In the framework of development ITER neutral beam (NB) system, a test facility is planned to be built in Padova. A full size prototype heating NB injector (MITICA) shall and tested at power (17 MW) as per requirements. The design MITICA source has further progressed following updated optimization overall integration criteria. paper, major choices revisions are presented, together with some results numerical analyses carried out order assess electrostatic thermo-mechanical behaviour source.