A5068152197- Magnetic confinement fusion research
- Particle accelerators and beam dynamics
- Superconducting Materials and Applications
- Plasma Diagnostics and Applications
- Particle Accelerators and Free-Electron Lasers
- Silicon Carbide Semiconductor Technologies
- HVDC Systems and Fault Protection
- Advanced DC-DC Converters
- Semiconductor materials and devices
- Advanced Data Storage Technologies
- Fusion materials and technologies
- Electromagnetic Launch and Propulsion Technology
- Silicon and Solar Cell Technologies
- Graphite, nuclear technology, radiation studies
- Thin-Film Transistor Technologies
- Advanced Data Processing Techniques
- Magneto-Optical Properties and Applications
- Wireless Power Transfer Systems
- Real-time simulation and control systems
- Superconductivity in MgB2 and Alloys
- Electric Power Systems and Control
- CCD and CMOS Imaging Sensors
- Nuclear reactor physics and engineering
- Radiative Heat Transfer Studies
- Advanced Optical Sensing Technologies
National Agency for New Technologies, Energy and Sustainable Economic Development
2011-2024
University of Padua
2019-2023
ASM International
2002
General Electric (United States)
1967-1979
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 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 use of one or more floating field limiting rings reduces the adverse effect junction curvature on breakdown voltage in planar devices. Although this has been known for some time, there not a way accurately predicting amount improvement that can be achieved using rings. In paper, computer algorithm is presented which makes it possible to perform calculations devices with addition, normalized curve shows relative single optimally placed ring any device. basis construction radius precise...
This paper presents the development and testing of prototype a hybrid mechanical-static dc circuit breaker (CB) for quench protection superconducting magnets based on mechanical switch paralleled to static CB. In normal operation, is closed it handles continuous flow current, minimizing on-state losses. case intervention, opens, commutating current into CB that quickly interrupts transfers discharge resistor, withstanding reapplied voltage. was carried out face solve some issues this design...
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...
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...
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.
The Fast Discharge Units (FDUs) of the Superconducting (SC) Toroidal Field (TF) coils in European demonstration fusion power plant DEMO warrant machine integrity over its full lifetime against severe failure events, such as SC coil quenches or any other events requiring safe TF magnet system discharge. A low (75 kA) and a high current (105 configuration are under study for DEMO. FDUs must be extremely reliable purpose commutating short time (∼1 s) currents to discharge magnets safely into...
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...