A. De Lorenzi
A5018893080- Particle accelerators and beam dynamics
- Magnetic confinement fusion research
- Plasma Diagnostics and Applications
- Superconducting Materials and Applications
- Vacuum and Plasma Arcs
- Electrostatic Discharge in Electronics
- Ionosphere and magnetosphere dynamics
- Fusion materials and technologies
- Particle Accelerators and Free-Electron Lasers
- High voltage insulation and dielectric phenomena
- Lightning and Electromagnetic Phenomena
- Radiation Effects in Electronics
- Particle Detector Development and Performance
- Nuclear Physics and Applications
- Power Transformer Diagnostics and Insulation
- Laser-Plasma Interactions and Diagnostics
- Silicon Carbide Semiconductor Technologies
- Gyrotron and Vacuum Electronics Research
- Semiconductor materials and devices
- Plasma and Flow Control in Aerodynamics
- Pulsed Power Technology Applications
- Magnetic Field Sensors Techniques
- Fluid Dynamics and Mixing
- Respiratory Support and Mechanisms
- Electromagnetic Launch and Propulsion Technology
National Agency for New Technologies, Energy and Sustainable Economic Development
2015-2024
Institute for the Science and Technology of Plasmas
2021-2024
University of Padua
1995-2023
European Society for Organ Transplantation
2014
University of Milan
2013
Japan Atomic Energy Agency
2012
Institute of Ionized Gas
1991-1998
University of Oxford
1997
Hospital Privado de Comunidad
1994
University of Buenos Aires
1994
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...
The spacers for the gas insulated transmission line ITER neutral beam injector will be designed to withstand operating voltage of 1 MV dc. Electric charging processes spacer surface are then expected play an important role in final electric field distribution. Aim paper is investigate effects different conductivity properties SF6-Spacer insulating structures on charge set-up, and identify a procedure minimize this charge. Based most updated literature, presents discusses results two newly...
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...
RFX-mod is a reversed field pinch (RFP) experiment equipped with system that actively controls the magnetic boundary. In this paper we describe results of new control algorithm, clean mode (CMC), in which aliasing sideband harmonics generated by discrete saddle coils corrected real time. CMC operation leads to smoother (i.e. more axisymmetric) Tearing modes rotate (up 100 Hz) and partially unlock. Plasma–wall interaction diminishes due decrease non-axisymmetric shift plasma column. With...
With the exploration of MA plasma current regime in up to 0.5 s long discharges, RFX-mod has opened new and very promising perspectives for reversed field pinch (RFP) magnetic configuration, made significant progress understanding improving confinement controlling stability. A big leap with respect previous knowledge expectations on RFP physics performance been by since last 2006 IAEA Fusion Energy Conference. self-organized helical equilibrium experimentally achieved (the Single Helical...
Optimization of machine operation, including plasma position control, density control and especially feedback on multiple magnetohydrodynamic modes, has led RFX-mod to operate reliably at 1.5 MA, the highest current ever achieved a reversed field pinch (RFP). At high low magnetic topology spontaneously self-organizes in an Ohmical helical symmetry, with new axis helically twisting around geometrical torus. The separatrix island disappears leaving wide symmetric thermal structure large...
This paper reports the main recent results of RFX-mod fusion science activity.The device is characterized by a unique flexibility in terms accessible magnetic configurations.Axisymmetric and helically shaped Reversed-field pinch equilibria have been studied, along with tokamak plasmas wide range q(a) regimes (spanning from 4 down to 1.2 values).The full configurations between two, so-called ultra low-q ones, has explored, aim studying specific physical issues common all equilibria, such as,...
The modified RFX is a very flexible device used for variety of control schemes MHD instabilities and advanced reverse field pinch scenarios. Relative to the previous machine, RFX-mod has thin Cu shell with vertical penetration time τS, lowered from 450 50 ms shell/plasma proximity b/a = 1.24–1.1. Toroidal equilibrium feedback-controlled new power supplies provide better B control. Newly designed graphite tiles protect vessel localized deposition. A mesh 192 external saddle coils, supervised...
This paper summarizes the main achievements of RFX fusion science program in period between 2008 and 2010 IAEA Fusion Energy Conferences. RFX-mod is largest reversed field pinch world, equipped with a system 192 coils for active control MHD stability. The discovery understanding helical states electron internal transport barriers core temperature >1.5 keV significantly advances perspectives configuration. Optimized experiments plasma current up to 1.8 MA have been realized, confirming...
The voltage holding in the 1 MV ITER Neutral Beam Accelerator is recognized to be one of most critical issues for long lasting beam operation, due complex electrostatic structure formed by differently shaped electrodes polarized at different potentials. At present, no model available predict breakdown probability system with a comparable complexity degree. This paper aimed proposing an innovative modelling prediction such systems, based on implementation micro particle (clump) induced...
In the framework of program for construction—in Padova, Italy—of first prototype International Thermonuclear Experimental Reactor 1 MeV–16 MW negative neutral beam injector (NNBI), an R&D activity on voltage holding in vacuum has been initiated since 2009, aimed at supporting design, construction, and development NNBI accelerator. For this purpose, high-voltage Padova test facility, designed to operate up 800 kV, built, parallel a multivoltage multielectrode prediction model (VHPM). This...