A5013677198- Superconducting Materials and Applications
- Magnetic confinement fusion research
- Particle accelerators and beam dynamics
- Fusion materials and technologies
- Nuclear reactor physics and engineering
- Physics of Superconductivity and Magnetism
- Nuclear Materials and Properties
- Spacecraft and Cryogenic Technologies
- Thermal Analysis in Power Transmission
- Nuclear Engineering Thermal-Hydraulics
- HVDC Systems and Fault Protection
- Plasma Diagnostics and Applications
- Gyrotron and Vacuum Electronics Research
- Solar Thermal and Photovoltaic Systems
- Nuclear Physics and Applications
- Superconductivity in MgB2 and Alloys
- Computational Fluid Dynamics and Aerodynamics
- Magnetic Properties and Applications
- Laser-Plasma Interactions and Diagnostics
- Particle Accelerators and Free-Electron Lasers
- Phase Change Materials Research
- Advanced Numerical Methods in Computational Mathematics
- Modeling and Simulation Systems
- Ionosphere and magnetosphere dynamics
- Photovoltaic System Optimization Techniques
Polytechnic University of Turin
2016-2025
University of Rome Tor Vergata
2024
National Agency for New Technologies, Energy and Sustainable Economic Development
1997-2023
École Polytechnique
2022
École Polytechnique Fédérale de Lausanne
2021
Ferrari (Italy)
2020
Royal Military Academy
2020
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2018
University of Turin
2006-2016
Turin Polytechnic University
2016
Falling particle receivers are being evaluated as an alternative to conventional fluid-based solar enable higher temperatures and efficiency power cycles with direct storage for concentrating (CSP) applications. This paper presents studies of the mass flow rate, velocity, particle-curtain opacity density, other characteristics free-falling ceramic particles a function different discharge slot apertures. The methods characterize described, results compared theoretical numerical models...
We present the pre-concept design of European DEMO Magnet System, which has successfully passed plant-level gate review in 2020. The main input parameters originate from so-called 2018 baseline, was produced using PROCESS systems code. It defines a major and minor radius 9.1 m 2.9 m, respectively, an on-axis magnetic field 5.3 T resulting peak on toroidal (TF) conductor 12.0 T. Four variants, all based low-temperature superconductors (LTS), have been designed for 16 TF coils. Two these...
The DEMO reactor is expected to be the first application of fusion for electricity generation in near future. To this aim, conceptual design activities are progressing Europe (EU) under lead EUROfusion Consortium order drive on development major tokamak systems. In 2014, carried out by magnet system project team were focused toroidal field (TF) and demonstrated achievements terms concept proposals consolidated evaluations against criteria. Several R&D conducted parallel, together with broad...
The European DEMO, i.e. the demonstration fusion power plant designed in framework of Roadmap to Fusion Electricity by EUROfusion Consortium, is approaching end pre-conceptual design phase, be accomplished with a Gate Review 2020, which all DEMO subsystems will reviewed panels independent experts. latest 2018 baseline has major and minor radius 9.1 m 2.9 m, plasma current 17.9 MA, toroidal field on axis 5.2 T, peak toroidal-field (TF) conductor 12.0 T. 900 ton heavy TF coil prepared four...
The Central Solenoid Model Coil (CSMC) was designed and built from 1993 to 1999 by an ITER collaboration between the U.S. Japan, with contributions European Union Russian Federation. main goal of project establish superconducting magnet technology necessary for a large-scale fusion experimental reactor. Three heavily instrumented insert coils were cover wide operational space testing. CS Insert, tested in April-August 2000. TF Federation, will be fall 2001. NbAl 2002. testing takes place...
<para xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink"> Four <formula formulatype="inline"><tex>${\rm Nb}_{3}{\rm Sn}$</tex> </formula> conductor lengths were prepared according to the ITER TF design and assembled into two SULTAN samples. The four are not fully identical, with variations of strand supplier, void fraction twist pitch. Lower fractions improve support increased pitches also lower contact pressure but both tend increase AC loss increases...
The ITER central solenoid (CS) is a highly stressed magnet that must provide 30 000 plasma cycles under the prescribed maximum operating conditions. To verify performance of CS conductor in conditions close to those for CS, insert was built USA-Japan collaboration. tested aperture CSMC facility Naka, Japan, during first half 2015. A magnetic field up 13 T and transport current 60 kA provided wide range parameters characterize conductor. has been direct reverse charges, which allowed strain...
Reliable analyses of thermal–hydraulic (TH) transients are becoming fundamental to supporting the design magnets for fusion applications based on high temperature superconducting (HTS) cable-in-conduit-conductors (CICCs). However, currently available TH codes were developed and validated only analysis wound with low superconductor (LTS) CICCs. In order confirm applicability such tools HTS CICCs, a two-step strategy is presented in this paper. First, qualitative assessment characteristic time...
Abstract In this work, we study the effect of installing a liquid metal divertor (LMD) using capillary-porous structure in EU DEMO tokamak within same envelope baseline solid divertor. We used SOLPS-ITER code to model scrape-off layer (SOL) plasma and neutrals, coupled target thermal enable self-consistent calculation LM erosion rate, adopting fluid neutral for sake simplicity. First calculations considering only D Li (or Sn) showed significant reduction steady state heat load with respect...
The expected increase in energy production from VRE (Variable Renewable Energy) requires a significant storage capacity, with thermal potentially offering key contribution. However, heat transfer mechanisms can limit the maximum power instantaneously transferable to medium, posing operational challenge. An analysis is presented here of limitations that arise when molten salt adopting Solar Salt (NaNO3/KNO3, 60/40%wt) heated by electrical resistances (Joule heating), and possible...
The world's largest pulsed superconducting coil was successfully tested by charging up to 13 T and 46 kA with a stored energy of 640 MJ. ITER central solenoid (CS) model CS insert were developed fabricated through an international collaboration, their cooldown tests carried out test operation teams. In tests, where the original goal 0.4 T/s T, achieved ramp rates 0.6 1.2 T/s, respectively. addition, charged discharged 10 003 times in background field no degradation operational temperature...
Safety studies are performed in the frame of conceptual design for European Demonstration Fusion Power Plant (DEMO) to assess safety and environmental impact options. An exhaustive set reference accident sequences defined order evaluate plant response most challenging events compliance with requirements. The Functional Failure Mode Effect Analysis (FFMEA) has been chosen as analytical tool, it is a suitable methodology define possible initiators when insufficient detail available allow more...
A short sample of the NbTi cable-in-conduit conductor (CICC) manufactured for ITER PF insert coil has been tested in SULTAN facility at CRPP. The consists two paired sections, identical except sub-cable and outer wraps, which have removed from one sections before jacketing. test program joint includes DC performance, cyclic load AC loss, with a large number voltage taps Hall sensors current distribution. At high operating current, behavior is well below expectations, temperature margin lower...