M. Dalla Palma
A5086226301- Particle accelerators and beam dynamics
- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Fusion materials and technologies
- Plasma Diagnostics and Applications
- Particle Accelerators and Free-Electron Lasers
- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Particle Detector Development and Performance
- Laser-Plasma Interactions and Diagnostics
- Ionosphere and magnetosphere dynamics
- Radiation Detection and Scintillator Technologies
- Nuclear and radioactivity studies
- Power Line Communications and Noise
- Gyrotron and Vacuum Electronics Research
- Fatigue and fracture mechanics
- Advanced Materials Characterization Techniques
- Seismology and Earthquake Studies
- Multimedia Communication and Technology
- Mechanical and Thermal Properties Analysis
- Wireless Communication Networks Research
- Geophysics and Sensor Technology
- Gas Dynamics and Kinetic Theory
- Non-Destructive Testing Techniques
National Agency for New Technologies, Energy and Sustainable Economic Development
2015-2024
Institute for the Science and Technology of Plasmas
2020-2024
University of Padua
1996-2024
University of Rome Tor Vergata
2024
National Research Council
2018-2022
National Academies of Sciences, Engineering, and Medicine
2022
ITER
2017
Institute of Ionized Gas
2011-2016
University of Milan
2013
Telecom Italia (Italy)
2008-2011
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 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...
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...
Borated water is used as a shield in nuclear fusion cooling circuits. General corrosion, activated corrosion products (ACPs) formation and stress cracking initiation of 316 L steels exposed to ultrapure (UPW) or 8000 ppm B at 80 °C were tested. A Ni enriched sub-oxide layer, transition layer oxide observed using advanced characterisation (STEM-EELS, APT). The formed UPW was protective (Cr:O 40:45), the non-passivating. led higher release Fe, Cr Mo, more prone SCC enhanced ACPs formation.
The ITER heating neutral beam (HNB) injector, based on negative ions accelerated at 1 MV, will be tested and optimized in the SPIDER source MITICA full injector prototypes, using a set of diagnostics not available HNB. RF source, where H−/D− production is enhanced by cesium evaporation, monitored with thermocouples, electrostatic probes, optical emission spectroscopy, cavity ring down, laser absorption spectroscopy. analyzed cooling water calorimetry, short pulse instrumented calorimeter,...
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...
Giant negative ion sources for neutral beam injectors deliver huge currents, thanks to their multi-beamlet configuration. As the single-beamlet optics defines transmission losses along beamline, extraction of a similar current all beamlets is extremely desirable, in order facilitate source operation (i.e., around perveance match). This Review investigates correlation between vertical profile intensity and profiles plasma properties at region source, focusing on influence increasing cesium...
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....
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 ITER neutral beam test facility under construction in Padova will host two experimental devices: SPIDER, a 100 kV negative H/D RF source, and MITICA, full scale, 1 MeV deuterium injector. Detection of fusion neutrons be used as means to resolve the horizontal intensity profile. neutron detection system placed right behind SPIDER dump, close emitting surface possible thus providing map emission on dump surface. uses nGEM detectors. These are Gas Electron Multiplier detectors equipped with...
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 ITER project requires additional heating provided by two neutral beam injectors using 40 A negative deuterium ions accelerated at 1 MV. As the requirements have never been experimentally met, a test facility is under construction Consorzio RFX, which hosts experiments: SPIDER, full-size 100 kV ion source prototype, and MITICA, MeV injector prototype. Since diagnostics in will be mainly limited to thermocouples, due neutron gamma radiation access, it crucial thoroughly investigate...
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...
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...