A5062773444- Particle accelerators and beam dynamics
- Magnetic confinement fusion research
- Plasma Diagnostics and Applications
- Particle Accelerators and Free-Electron Lasers
- Superconducting Materials and Applications
- Fusion materials and technologies
- Electrostatic Discharge in Electronics
- Atomic and Molecular Physics
- Ionosphere and magnetosphere dynamics
- Mass Spectrometry Techniques and Applications
- Radiation Effects in Electronics
- Solar and Space Plasma Dynamics
- Nuclear Physics and Applications
- Gyrotron and Vacuum Electronics Research
- Metal and Thin Film Mechanics
- Laser-induced spectroscopy and plasma
- Pulsed Power Technology Applications
- Spacecraft and Cryogenic Technologies
- Scientific Measurement and Uncertainty Evaluation
- Ultrasonics and Acoustic Wave Propagation
- High voltage insulation and dielectric phenomena
- Earthquake Detection and Analysis
- Muon and positron interactions and applications
- Cryptographic Implementations and Security
- Computational Fluid Dynamics and Aerodynamics
ITER
2018-2024
Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Legnaro
2009-2023
National Agency for New Technologies, Energy and Sustainable Economic Development
2011-2021
University of Padua
2013-2021
Istituto Nazionale di Fisica Nucleare
2015
Institute of Market Economy, Social Policy and Law
2013-2015
University of Milan
2013
Japan Atomic Energy Agency
2012
CEA Cadarache
2009
Laboratoire Plasma et Conversion d'Energie
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...
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...
Giant negative ion sources for neutral beam injectors deliver huge currents, thanks to their multi-beamlet configuration. As the single-beamlet optics defines transmission losses along beamline, extraction of a similar current all beamlets is extremely desirable, in order facilitate source operation (i.e., around perveance match). This Review investigates correlation between vertical profile intensity and profiles plasma properties at region source, focusing on influence increasing cesium...
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....
Abstract This paper explores the operational boundaries and power availability of neutral beam injection (NBI) system in ITER, with a specific focus on shine-through loss prevention. Shine-through, phenomenon where part injected remains un-ionized plasma directly impacts first wall components, poses significant risk to lifetime ITER’s plasma-facing components. The window for NBI is consequently constrained by these losses, which are influenced factors such as density, energy, geometry....
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...
Recent research results on negative-ion-rich plasmas in a large negative ion source have been reviewed. Spatial density and flow distributions of hydrogen ions (H−) positive together with those electrons are investigated 4-pin probe photodetachment (PD) signal Langmuir probe. The PD is converted to local H− from calibration scanning cavity ring down measurement. Introduction Cs changes the slope plasma potential distribution depending upon grid bias. A higher electron H2 locally shields bias...
Abstract A low beamlet divergence is crucial for the efficiency of ITER-NBI systems, since it affects transmission beam through duct. There a requirement 7 mrad e -folding ITER Heating Neutral Beam. Significantly higher divergences (10–15 mrad) have been observed in RF-source based experiments albeit at energy. This could be consequence broad perpendicular velocity distribution H − /D particles before extraction. paper explores this hypothesis and its implications ITER. To estimate...
Neutral Beam Injectors (NBIs), which need to be strongly optimized in the perspective of DEMO reactor, request a thorough understanding negative ion source used and multi-beamlet optics. A relatively compact radio frequency (rf) source, named NIO1 (Negative Ion Optimization 1), with 9 beam apertures for total H− current 130 mA, 60 kV acceleration voltage, was installed at Consorzio RFX, including high voltage deck an X-ray shield, provide test bench optimizations activities support ITER NBI...