D. Marcuzzi
A5085622855- Magnetic confinement fusion research
- Particle accelerators and beam dynamics
- Superconducting Materials and Applications
- Plasma Diagnostics and Applications
- Particle Accelerators and Free-Electron Lasers
- Fusion materials and technologies
- Ionosphere and magnetosphere dynamics
- Nuclear Physics and Applications
- Plasma and Flow Control in Aerodynamics
- Solar and Space Plasma Dynamics
- Magnetic Field Sensors Techniques
- Electrostatic Discharge in Electronics
- Muon and positron interactions and applications
- Atomic and Molecular Physics
- Quantum chaos and dynamical systems
- Metal and Thin Film Mechanics
- Magnetic Properties and Applications
- Gyrotron and Vacuum Electronics Research
- Laser-Plasma Interactions and Diagnostics
National Agency for New Technologies, Energy and Sustainable Economic Development
2015-2024
University of Padua
2015-2023
University of Milan
2013
Japan Atomic Energy Agency
2012
Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Legnaro
2009-2011
Université Toulouse III - Paul Sabatier
2009
Centre National de la Recherche Scientifique
2009
CEA Cadarache
2009
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2009
Institute for Plasma Research
2009
The ITER neutral beam (NB) injectors are the first that will have to operate under conditions and constraints similar those be encountered in a fusion reactor. These hostile radiation environment they become highly radioactive due neutron flux from ITER. use single large ion source accelerator produce 40 A 1 MeV D − beams for pulse lengths of up 3600 s. Significant design changes been made heating NB (HNB) injector over past 4 years. main are: Modifications allow installation maintenance...
The heating neutral beam injectors (HNBs) of ITER are designed to deliver 16.7 MW 1 MeV D0 or 0.87 H0 the plasma for up 3600 s. They will be most powerful (NB) ever, delivering higher energy NBs in a tokamak longer than any previous systems have done. design HNBs is based on acceleration and neutralisation negative ions as efficiency conversion accelerated positive so low at required that realistic not possible, whereas H− D− remains acceptable (≈56%).
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...
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 ITER is of key importance in the European fusion roadmap as it aims to prove scientific and technological feasibility a future energy source. The EUROfusion consortium labs within Europe contributing preparation exploitation operation aspires exploit outcomes view DEMO. paper provides an overview major progress obtained recently, carried out frame new (initiated 2021) work-package called ‘ Pr eparation I TER O peration’ (PrIO). directly supported by eleven PrIO contributions given...
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 device that allowed performing experiments in regimes with plasma current up to 2 MA, thanks its MHD active control system. Experiments have shown improved performances are obtained when the resonant part of m = 1 spectrum one dominant tearing mode much higher than other secondary ones (quasi single helicity states). Tearing modes play crucial role determining energy and particle transport. Based on present understanding interplay between passive conductive...
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....
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...
An improvement for the vacuum system of multidriver radio frequency (RF) prototype negative ion source SPIDER has been developed, to allow operating at high RF power, while minimizing breakdown probability on outside plasma source. A first-of-its-kind large nonevaporable getter (NEG) pump, based a modular design 384 cartridges totaling about 350 kg ZAO® alloy (composed by Zr-Ti-V-Al) with an installed pumping speed room temperature 330 m3/s hydrogen, will complement existing system, eight...