N. Fonnesu
A5062693867- Magnetic confinement fusion research
- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- Particle accelerators and beam dynamics
- Fusion materials and technologies
- Particle Accelerators and Free-Electron Lasers
- Plasma Diagnostics and Applications
- Superconducting Materials and Applications
- Nuclear Materials and Properties
- Radiation Therapy and Dosimetry
- Radiation Detection and Scintillator Technologies
- Atomic and Subatomic Physics Research
- Ion-surface interactions and analysis
- Graphite, nuclear technology, radiation studies
- Diamond and Carbon-based Materials Research
- High-pressure geophysics and materials
- Boron Compounds in Chemistry
- Radiation Shielding Materials Analysis
- Radiation Effects in Electronics
- X-ray Spectroscopy and Fluorescence Analysis
- Muon and positron interactions and applications
- Advanced Radiotherapy Techniques
National Agency for New Technologies, Energy and Sustainable Economic Development
2015-2024
University of Rome Tor Vergata
2016-2019
University of Padua
2012-2015
Sapienza University of Rome
2012
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 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...
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...
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...
Abstract Neutral beam injectors are among the most important methods of plasma heating in magnetic confinement fusion devices. The propagation negative ions, prior to their conversion into neutrals, is fundamental importance determining properties beam, such as its aiming and focusing at long-distances, so deposit power proper position inside confined plasma, well avoid interaction with material surfaces along path. final design ITER Heating Beam prototype has been completed Consorzio RFX...
Neutronics benchmark experiments are conducted at JET in the frame of WPJET3 NEXP within EUROfusion Consortium for validating neutronics codes and tools used ITER nuclear analyses to predict quantities such as neutron flux along streaming paths dose rates shutdown due activated components. The preparation rate future Deuterium-Tritium operations (DTE2 campaign) progress. This paper summarizes status measurements progress current Deuterium–Deuterium (DD) campaign efforts DTE2.
This paper reports about the performances of single crystal diamond (SCD) detectors operated at high temperature (up to 200 <formula formulatype="inline" xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink"> <tex Notation="TeX">$^{\circ}$</tex></formula> C) and irradiated with alpha particles. Two different types SCD were studied: a) commercial type; b) produced Rome "Tor Vergata" University characterized by a layered structure.
This paper reports the highlights of RFX-mod fusion science programme since last 2010 IAEA Fusion Energy Conference. The focused on two main goals: exploring potential reversed field pinch (RFP) magnetic configuration and contributing to solution key technology problems in roadmap ITER. Active control several plasma parameters has been a tool this endeavour. New upgrades system for active magnetohydrodynamic (MHD) stability are underway will be presented paper. Unique among existing devices,...
The ITER project requires additional heating provided by two injectors of neutral beams resulting from the neutralisation accelerated negative ions. To study and optimise ion production, SPIDER test facility (particle energy 100keV; beam current 50A) is under construction in Padova, with aim testing characteristics to verify source proper operation. will be characterised instrumented calorimeter STRIKE, whose main components are one-directional carbon fibre composite tiles. Some prototype...
The thermo-mechanical analysis and the mechanical design of accelerator MITICA (i.e. full size prototype ITER neutral beam injector under construction at RFX [1]) are based on calculation power deposition induced by particle impacts. This is performed EAMCC [2], a relativistic tracking code Monte-Carlo method for describing collisions inside accelerator, prescribed electric magnetic fields. field maps produced 3D codes, while come from 2D axi-symmetric SLACCAD [3]. In order to perform...
The Radial Neutron Camera (RNC) is a diagnostic system located in the ITER Equatorial Port 1 (EP01) composed by two sub-systems (i.e.: in-port and ex-port RNC) probing poloidal section of plasma through set fan-shaped Lines Sight (LOS). RNC designed to provide time resolved measurement neutron alpha particles source profiles total strength, application reconstruction techniques line-integrated fluxes. Ex-port sub-system 16 LOS distributed different toroidal planes enclosed massive shielding...
The SORGENTINA-RF project aims at developing a 14 MeV fusion neutron source featuring an emission rate in the order of 5–7 × 1013 s−1. plant relies on metallic water-cooled rotating target and deuterium (50%) tritium ion beam. Beyond main focus medical radioisotope production, may represent multi-purpose facility by implementing series neutron-based techniques. Among different engineering technological issues to be addressed, production incondensable gases corrosion product into deserves...