G. Gambetta
A5016554329- Particle accelerators and beam dynamics
- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Particle Accelerators and Free-Electron Lasers
- Plasma Diagnostics and Applications
- Fusion materials and technologies
- Electrostatic Discharge in Electronics
- Magnetic Field Sensors Techniques
- Atomic and Molecular Physics
- Gas Dynamics and Kinetic Theory
- Atomic and Subatomic Physics Research
- Laser-Plasma Interactions and Diagnostics
- Spacecraft and Cryogenic Technologies
National Agency for New Technologies, Energy and Sustainable Economic Development
2015-2020
University of Padua
2015-2020
ITER
2020
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...
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 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 measurements of the magnetic field in tokamaks such as ITER and DEMO will be challenging due to long pulse duration, high neutron flux, elevated temperatures. duration plasma makes standard techniques, inductive coils, prone errors. At same time, hostile environment, with repairs possible only on blanket exchange, if at all, requires a robust sensor. This contribution presents final design novel, steady-state, sensors for ITER. A poloidal array 60 mounted vacuum vessel outer shell...
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.