A5021632914- 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
- Liver Disease and Transplantation
- Metal and Thin Film Mechanics
- Organ Transplantation Techniques and Outcomes
- Liver Disease Diagnosis and Treatment
- Atomic and Molecular Physics
- Electrostatic Discharge in Electronics
- Ion-surface interactions and analysis
- Laser-Plasma Interactions and Diagnostics
- Ionosphere and magnetosphere dynamics
- Sleep and Work-Related Fatigue
- Magnetic Field Sensors Techniques
- Sleep and related disorders
National Agency for New Technologies, Energy and Sustainable Economic Development
2015-2024
University of Padua
2012-2023
Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Legnaro
2017-2021
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...
Abstract An overview is presented of the progress since 2021 in construction and scientific programme preparation Divertor Tokamak Test (DTT) facility. Licensing for building has been granted at end 2021. Cat. A radiologic source also 2022. The toroidal field magnet system progressing. prototype 170 GHz gyrotron produced it now under test on FALCON design vacuum vessel, poloidal coils civil infrastructures completed. shape first DTT divertor agreed with EUROfusion to different plasma exhaust...
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....
A new magnetic configuration is proposed for the suppression of co-extracted electrons in a negative-ion accelerator. This produced by an arrangement permanent magnets embedded one accelerator grid and creates asymmetric local field on upstream downstream sides this grid. Thanks to "concentration" side grid, resulting deflection ions due can be "intrinsically" cancelled calibrating magnets. At same time, improved.
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,...
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...
Electroencephalography (EEG) is useful to objectively diagnose/grade hepatic encephalopathy (HE) across its spectrum of severity. However, it requires expensive equipment, and hepatogastroenterologists are generally unfamiliar with acquisition/interpretation. Recent technological advances have led the development low‐cost, user‐friendly EEG systems, allowing acquisition also in settings limited neurophysiological experience. The aim this study was assess relationship between parameters...
Abstract Neutral beam injectors are among the most important methods of plasma heating in magnetic confinement fusion devices. The propagation negative ions, prior to their conversion into neutrals, is fundamental importance determining properties beam, such as its aiming and focusing at long-distances, so deposit power proper position inside confined plasma, well avoid interaction with material surfaces along path. final design ITER Heating Beam prototype has been completed Consorzio RFX...
The design of the magnetic field configuration in SPIDER and MITICA negative ion beam sources has evolved considerably during past four years. This evolution was driven by three factors: 1) experimental results large RF-driven at IPP, which have provided valuable indications on optimal configurations for reliable RF plasma source operation current extraction, 2) comprehensive optics heat load simulations, showed that accelerator is crucial keeping due to electrons grids within tolerable...
An innovative magnetic configuration called ADCM (Asymmetric Deflection Compensation Magnets) has been recently proposed for the cancellation of "criss-cross" deflection ion trajectories in multi-beamlet negative accelerators. Such undesired occurs due to transverse field, which is necessary suppression co-extracted electrons. In view application this concept ITER Heating Neutral Beam Injector, new experimentally tested first time 2016, framework a research collaboration between Consorzio...
In June 2018 the SPIDER device, which is full-size prototype of negative ion source and extractor for ITER Heating Neutral Beam has entered first operation phase at Test Facility (NBTF) in Padova, Italy. This paper describes present status experimental plans results obtained during campaign radio-frequency driven plasma source.
The electrical insulation of the Megavolt ITER Injector and Concept Advancement (MITICA) beam source (BS) at 1 MV in vacuum is a challenging issue, which could not be fully addressed so far on basis experimental results theoretical models available literature. A specific high-voltage (HV) test campaign being prepared to validate optimize voltage holding capability BS under realistic conditions, using full-size mockup electrodes reproducing detail geometry accelerator. proposed strategy will...