A5017177496- Particle accelerators and beam dynamics
- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Plasma Diagnostics and Applications
- Particle Accelerators and Free-Electron Lasers
- Fusion materials and technologies
- HVDC Systems and Fault Protection
- Structural Behavior of Reinforced Concrete
- Structural Analysis of Composite Materials
- Silicon Carbide Semiconductor Technologies
- Pulsed Power Technology Applications
- High voltage insulation and dielectric phenomena
- Innovative concrete reinforcement materials
- Engineering Applied Research
- Superconductivity in MgB2 and Alloys
- Atomic and Molecular Physics
- Structural Load-Bearing Analysis
- Structural Analysis and Optimization
- Masonry and Concrete Structural Analysis
National Agency for New Technologies, Energy and Sustainable Economic Development
2018-2024
Hefei University of Technology
2024
University of Padua
1989-2023
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 European DEMO, i.e. the demonstration fusion power plant designed in framework of Roadmap to Fusion Electricity by EUROfusion Consortium, is approaching end pre-conceptual design phase, be accomplished with a Gate Review 2020, which all DEMO subsystems will reviewed panels independent experts. latest 2018 baseline has major and minor radius 9.1 m 2.9 m, plasma current 17.9 MA, toroidal field on axis 5.2 T, peak toroidal-field (TF) conductor 12.0 T. 900 ton heavy TF coil prepared four...
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....
The EU DEMO Plant Electrical System (PES) main scopes are to supply all the plant electrical loads and deliver Power Transmission Grid (PTG) net power generated. studies on PES during Pre-Concept Design (PCD) Phase were mainly addressed understand possible issues, related special features both of generated, with respect a same size, be supplied loads. For this purpose, approach was start design different components adopting technologies already utilized in fusion experiments Nuclear Plants...
The Plant Electrical System (PES) of the European DEMOnstration fusion power plant (DEMO), presently under conceptual design, shall supply to loads and deliver net Power Transmission Grid (PTG). Starting from available requirements, applicability DEMO PES technologies design approaches adopted in ITER nuclear plants (NPP) has been evaluated. This article presents results survey proposes alternative solutions deal with identified criticalities.
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...
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...
At the International Thermonuclear Experimental Reactor (ITER) Neutral Beam Test Facility in Padua (Italy), ion source full-scale prototype—SPIDER—has been operation since June 2018 and, as of March 2021, has begun to explore range beam energies exceeding 30 keV. This revealed a number novel issues with power supplies and extractor, mainly associated grid breakdowns. Those include set high current single quadrant resonant converters, known support (ISSSs) voltage pulse step modulator feeding...
Source for the production of ions deuterium extracted from a radio frequency plasma (SPIDER), full-scale prototype ion source ITER heating neutral beam (HNB) injector, started operation in June 2018. During first experimental phase, some issues concerned its novel and complex power supply system. Dedicated analyses studies, carried out to understand address them, resulted plant modifications be implemented during SPIDER major shutdown, late 2021. To assess validity conceived countermeasures,...
In SPIDER, the full-scale prototype of negative ion source ITER Heating Neutral Beam Injectors, ions hydrogen or deuterium are extracted and accelerated by a set grids. This article describes process technical solutions that allowed achieving asseveration to operate Acceleration Grid Power Supply SPIDER at full voltage (−96 kV), reports first experimental results, discusses some possible enhancements have been identified.