R. Villari
A5073809659- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Fusion materials and technologies
- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Nuclear Materials and Properties
- Particle accelerators and beam dynamics
- Radiation Detection and Scintillator Technologies
- Radiation Therapy and Dosimetry
- Graphite, nuclear technology, radiation studies
- Gyrotron and Vacuum Electronics Research
- Radiation Shielding Materials Analysis
- Particle Detector Development and Performance
- High-Energy Particle Collisions Research
- Ionosphere and magnetosphere dynamics
- Astrophysics and Cosmic Phenomena
- Nuclear and radioactivity studies
- Neutrino Physics Research
- Radiation Effects in Electronics
- Particle physics theoretical and experimental studies
- Laser-Plasma Interactions and Diagnostics
- Infrared Target Detection Methodologies
- Electromagnetic Compatibility and Noise Suppression
- Technology Assessment and Management
- Engineering Applied Research
National Agency for New Technologies, Energy and Sustainable Economic Development
2015-2024
Fusion for Energy
2024
CEA Cadarache
2011-2024
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2011-2024
University of Rome Tor Vergata
2024
Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Frascati
2005-2022
Università degli studi di Cassino e del Lazio Meridionale
2022
Culham Science Centre
2012-2021
Royal Military Academy
2020
Culham Centre for Fusion Energy
2017
Abstract The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations for neutron-induced interactions with the major actinides $$^{235}\hbox {U}$$ <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML"><mml:mrow><mml:msup><mml:mrow /><mml:mn>235</mml:mn></mml:msup><mml:mtext>U</mml:mtext></mml:mrow></mml:math> , $$^{238}\hbox /><mml:mn>238</mml:mn></mml:msup><mml:mtext>U</mml:mtext></mml:mrow></mml:math> $$^{239}\hbox {Pu}$$...
In a power plant scale fusion reactor, huge amount of thermal produced by the reaction and external heating must be exhausted through narrow area divertor targets. The targets withstand intense bombardment diverted particles where high heat fluxes are generated erosion takes place on surface. A considerable volumetric nuclear also exhausted. To cope with such an unprecedented exhaust challenge, highly efficient cooling capacity is required. Furthermore, fulfill other critical functions as...
The water-cooled lithium–lead breeding blanket is a candidate option for the European Demonstration Power Plant (DEMO) nuclear fusion reactor. This concept relies on liquid as breeder–multiplier, pressurized water coolant, and EUROFER structural material. current design based DEMO 2015 specifications represents follow-up of developed in 2015. single-module-segment approach employed. constituted by basic geometry repeated along poloidal direction. power removed means radial–toroidal (i.e.,...
The water-cooled lithium-lead (PbLi) breeding blanket is one of the candidate systems considered for implementation in European Demonstration Power Plant (DEMO) nuclear fusion reactor. This concept employs PbLi liquid metal as tritium breeder and neutron multiplier, water pressurized at 15.5 MPa coolant, EUROFER structural material. current design based on single module segment approach follows requirements DEMO-2015 baseline design. constituted by a basic toroidal-radial cell that...
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.
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...
FAST is a new machine proposed to support ITER experimental exploitation as well anticipate DEMO relevant physics and technology. aimed at studying, under burning plasma conditions, fast particle (FP) physics, operations wall interaction in an integrated way. has the capability approach all scenarios significantly closer than present day experiments using deuterium plasmas. The necessity of achieving performance with moderate cost led conceiving compact tokamak (R = 1.82m, 0.64m) high...
Since 2014 preconceptual design activities for European DEMO divertor have been conducted as an integrated, interdisciplinary R&D effort in the framework of EUROfusion Consortium. Consisting two subproject areas, 'Cassette' and 'Target', this project has objective to deliver a holistic concept together with key technological solutions materialize design. In paper, brief overview on recent results from is presented. subproject, overall cassette system engineered based load analysis...
Abstract The present paper is devoted to a first assessment of the DEMO diagnostics systems and controls in context pulsed steady state reactor design under study Europe. In particular, main arguments treated are: (i) quantities be measured requirements for measurements; (ii) capability diagnostic control technology, determining most urgent gaps, (iii) program strategy research development (R&D) needed fill gaps. Burn control, magnetohydrodynamic stability, basic machine protection...
Abstract JET returned to deuterium-tritium operations in 2023 (DTE3 campaign), approximately two years after DTE2. DTE3 was designed as an extension of JET's 2022-2023 deuterium campaigns, which focused on developing scenarios for ITER and DEMO, integrating in-depth physics understanding control schemes. These were evaluated with mixed D-T fuel, using the only remaining tritium-capable tokamak until its closure 2023. A core-edge-SOL integrated H-mode scenario developed tested D-T, showing...
Abstract Two neutronics experiments have been carried out at 14 MeV neutron sources on mock-ups of the helium cooled pebble bed (HCBP) and lithium lead (HCLL) variants ITER test blanket modules (TBMs). These provided an experimental validation calculations tritium production rate (TPR) in two concepts assessment uncertainties due to nuclear data. This paper provides a brief summary HCPB experiment then focuses particular final results HCLL experiment. The TPR has measured mock-up irradiated...