A5076129299- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Non-Destructive Testing Techniques
- Laser-Plasma Interactions and Diagnostics
- Geomagnetism and Paleomagnetism Studies
- Neural Networks and Applications
- Particle Accelerators and Free-Electron Lasers
- Plasma Diagnostics and Applications
- Gyrotron and Vacuum Electronics Research
- Magnetic Properties and Applications
- Electromagnetic Launch and Propulsion Technology
Università degli Studi della Tuscia
2022-2025
University of Padua
2024
University of Rome Tor Vergata
2024
Abstract This paper is dealing with the physics basis used for design of Divertor Tokamak Test facility (DTT), under construction in Frascati (DTT 2019 DTT interim report (2019)) Italy, and description main target plasma scenarios device. The goal will be study power exhaust, intended as a fully integrated core-edge problem, eventually to propose an optimized divertor European DEMO plant. approach described their features are reported, by using simulations performed state-of-the-art codes...
Tokamak Energy Ltd. is developing compact fusion power plants based on two promising technologies, Spherical Tokamaks (STs) and High Temperature Superconductors (HTS), with the aim to build a first demonstrative plant by 2030′s. On its path power, presently operating ST40, new generation ST that currently highest field device of kind. In near future, an important ST40 upgrade planned foresees manufacturing installation vacuum chamber, called IVC2. This will allow exploitation maximum...
The evaluation of electromagnetic (EM) behaviour tokamak components under disruption loads and its correlation with vertical instabilities is critical characterizing the design considerations. This particularly crucial for high-field burning plasma experiments such as SPARC tokamak, compact prototype currently construction by Commonwealth Fusion Systems (CFS). combination high toroidal magnetic field (12.2 T) current (8.7 MA) makes less tolerant to disruptions than operating research...
Nuclear fusion is entering the era of power plant-scale devices, which are now undergoing extensive studies to support design phase. Plasma disruptions pose a high risk these classes devices because large stored thermal and magnetic energy might jeopardize machine integrity availability. Therefore, within must be virtually eliminated, any do happen highly mitigated. However, characterisation, prediction technology used mitigate still an area active development. In this paper, authors...
Modelling the structural effects of vertical displacement events (VDEs) on plasma facing components is critical for component integrity but can be both computationally intensive and time consuming. In early-stage design, a simple analysis method useful to compare concepts. This paper describes methods that uses commercially available ANSYS software obtain estimations forces torques arising from VDE induced currents halo currents. The will used inform design in-vessel assemblies Tokamak...