A5022663456- Magnetic confinement fusion research
- Particle accelerators and beam dynamics
- Plasma Diagnostics and Applications
- Ionosphere and magnetosphere dynamics
- Solar and Space Plasma Dynamics
- Superconducting Materials and Applications
- Fusion materials and technologies
- Laser-Plasma Interactions and Diagnostics
- Particle Accelerators and Free-Electron Lasers
- Electrohydrodynamics and Fluid Dynamics
- Fluid Dynamics and Turbulent Flows
- Complex Systems and Time Series Analysis
- Theoretical and Computational Physics
- Metal and Thin Film Mechanics
- Laser-induced spectroscopy and plasma
- Plasma Applications and Diagnostics
- Advanced Data Storage Technologies
- Gyrotron and Vacuum Electronics Research
- Atomic and Molecular Physics
- Dust and Plasma Wave Phenomena
- Electrostatic Discharge in Electronics
- Plasma and Flow Control in Aerodynamics
- Earthquake Detection and Analysis
- Nuclear reactor physics and engineering
- Muon and positron interactions and applications
Institute for the Science and Technology of Plasmas
2020-2024
National Research Council
2024
National Agency for New Technologies, Energy and Sustainable Economic Development
2014-2023
University of Padua
1997-2023
Institute of Ionized Gas
1989-2019
Istituto Nazionale di Fisica Nucleare
2015
Institute of Market Economy, Social Policy and Law
2013-2015
Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Legnaro
2009-2013
University of Milan
2013
CEA Cadarache
2009
The ITER neutral beam injectors are the first to be designed operate under conditions and constraints similar those that will encountered with a fusion reactor. use single large ion source accelerator produce 40A D− 1MeV beams for pulse lengths of up 3600s. accelerated neutralized in gas (D2) neutralizer which is subdivided into four vertical channels reduce flow needed optimum target neutralization. These have hostile radiation environment they become highly radioactive due neutron flux...
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...
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...
Experiments in the tokamaks TEXTOR, CASTOR, T-10 and ISTTOK, as well reversed field pinch RFX have provided new complementary evidence on physics of universal mechanism E×B velocity shear stabilization turbulence, concomitant transport barrier formation radial conductivity by using various edge biasing techniques.
The rescaled range analysis techniques are used to investigate long-range dependence in plasma edge fluctuations [Mandelbrot and Wallis, Water Resources Res. 4, 909 (1969)]. This technology has been applied data from several confinement devices such as tokamaks, stellarators, reversed-field pinch. results reveal the self-similar character of electrostatic at with self-similarity parameters ranging 0.62 0.72. These show that tail autocorrelation function decays a power law for time lags...
The MHD current driven instabilities of Reversed Field Pinch (RFP) configurations are analysed for a plasma in contact with perfectly conducting wall. equilibrium distributions obtained on the basis model which allows parametric variation value safety factor axis, q(0), and density distribution. – RFP is found to be stable wide range parameters. However, when toroidal field reversal becomes too deep, unstable modes, resonant outside surface, analogy stability limit at θ = 1.56 Taylor's...
The ITER Neutral Beam Test Facility (PRIMA) is planned to be built at Consorzio RFX (Padova, Italy). PRIMA includes two experimental devices: a full size ion source with low voltage extraction called SPIDER and neutral beam injector power MITICA. the first device operated, aiming testing of negative (made H − in later stage D ions) from an source. main requirements this experiment are /D extracted current density larger than 355/285 A m −2 , energy 100 keV pulse duration up 3600 s. Several...
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...
Abstract The physics design of the accelerator for heating neutral beamline on ITER is now finished and this paper describes considerations choices which constitute basis design. Equal acceleration gaps 88 mm have been chosen to improve voltage holding capability while keeping beam divergence low. Kerbs (metallic plates around groups apertures, attached downstream surface grids) are used compensate beamlet–beamlet interaction point beamlets in right direction. A novel magnetic configuration...
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...
Two Neutral Beam Injectors (NBI) are foreseen to provide a substantial fraction of the heating power necessary ignite thermonuclear fusion reactions in ITER. The development NBI system at unprecedented parameters (40 A negative ion current accelerated up 1 MV) requires realization full scale prototype, be tested and optimized Test Facility under construction Padova (Italy). beam source is key component design multi-grid accelerator goal multi-national collaborative effort. In particular,...
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...
The electrostatic turbulence in the edge plasma of RFX reversed field pinch experiment has been studied using Langmuir probes and a homodyne reflectometer. radial particle flux driven by fluctuations measured region where double $\mathbf{E}\ifmmode\times\else\texttimes\fi{}\mathbf{B}$ velocity shear layer occurs. It is found that almost 100% at fluctuations. naturally occurring shown to be close required Biglari-Diamond-Terry criterion for decorrelation.
Coherent structures identified in two reversed field pinch experiments are interpreted as a dynamic balance of dipolar and monopolar vortices growing evolving under the effect ExB flow shear. For first time their contribution to anomalous transport has been estimated fusion related plasmas, showing that they can account for up 50% total plasma diffusivity. The experimental findings indicate diffusion coefficient associated with coherent depends on relative population types is minimum when...
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...
The first evidence of an electrostatic potential well at the edge plasmas confined in a reversed field pinch configuration is reported, based on measurements made RFX experiment. radial width decreases with plasma current, whereas drop few times electron temperature edge, almost independent current. resulting electric points inward and this behavior has been related to finite Larmor radius losses as tokamaks. Because spatial structure potential, naturally occurring double velocity shear...
A statistical analysis of the anomalous particle flux in edge region RFX experiment has revealed that laminar times between bursts, which account for more than 50% losses, have a power law distribution and fluctuations are not self-similar. These properties found contrast with wide class self-organized-criticality models so it is concluded there no experimental evidence avalanchelike process occurrence plasma RFX.