A5024924903- Particle accelerators and beam dynamics
- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Fusion materials and technologies
- Particle Accelerators and Free-Electron Lasers
- Plasma Diagnostics and Applications
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Nuclear and radioactivity studies
- Non-Destructive Testing Techniques
- Advanced Materials Characterization Techniques
- Nuclear Materials and Properties
National Agency for New Technologies, Energy and Sustainable Economic Development
2017-2024
Institute for the Science and Technology of Plasmas
2023-2024
University of Padua
2015-2024
National University of Distance Education
2022
National Research Council
2018
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 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 Pre-Concept Design (PCD) of the Balance Plant (BoP) systems EU-DEMO power plant is described in this paper for both breeding blanket (BB) concepts under assessment, namely Water Cooled Lithium Lead (WCLL) BB and Helium Pebble Bed (HCPB) BB. Moreover, results a preliminary evaluation number BoP variants are discussed. This outlines steps design development, highlighting project objectives strategy their achievement very challenging requirements which include, among others, intermittent...
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....
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...
An improvement for the vacuum system of multidriver radio frequency (RF) prototype negative ion source SPIDER has been developed, to allow operating at high RF power, while minimizing breakdown probability on outside plasma source. A first-of-its-kind large nonevaporable getter (NEG) pump, based a modular design 384 cartridges totaling about 350 kg ZAO® alloy (composed by Zr-Ti-V-Al) with an installed pumping speed room temperature 330 m3/s hydrogen, will complement existing system, eight...
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...
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 European DEMO is considered the nearest-term fusion reactor with aim to generate several hundred MWs of net electricity, operate a closed tritium fuel-cycle (achieving self-sufficiency) and qualify technological solutions for Fusion Power Plant. Two Breeding Blanket (BB) concepts - relying on different cooling breeding technologies are baseline design: Helium Cooled Pebble Bed (HCPB) BB Water Lithium Lead (WCLL) BB. selection type has strong impact whole plant design and, in particular,...
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.
Low divergence negative ion beams are crucial for the development of ITER-like fusion reactors. SPIDER is prototype beam source ITER heating neutral injector, and it recently started acceleration, up to a voltage 30 kV. The main diagnostics used measure beamlet movable diagnostic calorimeter (STRIKE), which gives thermal footprint beamlets; emission spectroscopy; visible imaging. These systems do not allow direct measurement single phase-space distribution, useful comparison with numerical...
Source for production of ion deuterium extracted from rf plasma (SPIDER) is the 100 keV negative source prototype ITER neutral beam injector. The cooling plant one SPIDER auxiliary systems where ultrapure water (UPW) used as media, thanks to its advantageous properties such good performance and high resistivity. Water resistivity needs be maintained above certain values during operation enable electrical insulation in-vessel components that operate at different voltages. Nonetheless,...
The beam power produced by the negative ion source for production of deuterium extracted from RF plasma is mainly absorbed dump component which has been designed also measuring temperatures on dumping panels diagnostics. A finite element code developed to characterize, thermo-hydraulic analysis, sensitivity different parameters. results prove capability diagnosing divergence and horizontal misalignment, while entity halo fraction appears hardly detectable without considering other foreseen...
Abstract Three years of experiments on SPIDER allowed characterization the main features source plasma and negative ion beam, in original design configuration. For large dimensions chamber, extraction area, investigation single-beamlet currents uniformity had to be carried out extend knowledge gained smaller prototype sources. The configuration multiple RF drivers filter field topologies were found cause a peculiar behavior confinement drivers, creating left-right asymmetries which also...