Description du projet
Une étude se penche sur la dynamique des ions rapides dans les réacteurs à fusion
Un tokamak est un type de dispositif de confinement magnétique utilisé dans les réacteurs afin de produire une énergie de fusion thermonucléaire contrôlée. L’un des principaux défis consiste à maintenir le plasma suffisamment chaud pour que la fusion puisse avoir lieu, tout en empêchant les parois du tokamak de fondre sous l’effet de la chaleur. Pour éviter tout dommage potentiel, les tokamaks doivent fonctionner sans présenter de risque d’instabilité de bord. Le comportement des ions énergétiques revêt une importance fondamentale pour l’étude des processus de fusion dans les réacteurs. Financé par le programme Actions Marie Skłodowska-Curie, le projet FICOP étudiera les mécanismes physiques fondamentaux qui régissent les interactions entre les instabilités de bord et le confinement des ions rapides. Les chercheurs s’intéresseront également aux conditions qui favorisent l’emballement des ions dans les tokamaks.
Objectif
The project presented here deals with Fast-Ion Confinement OPtimization (FICOP) in magnetically confined fusion reactors. The goal of the project presented here is the characterization of the effect of edge instabilities on fast-ion confinement and the understanding of the physical mechanisms behind this interaction, as well as to experimentally explore the conditions upon which ion runaway can take place in tokamaks by studying the behaviour of fast-ions in the current ramp-up and ramp-down phases, disruptions, and sawtooth crashes. To fulfill these objectives, novel and cutting-edge data analysis techniques will be developed to be applied to fusion diagnostics, including integrated tomography techniques and deep learning.
The results of this project are expected to have a direct impact on the fusion community. The problem of power exhaust in tokamaks mainly focuses on the power dissipation through the divertor plates. Therefore, the limits to tokamak operation are set based on the heat fluxes that the materials in the divertor plates can tolerate. However, an additional constraint might come from the fast-ion heat loads due to edge instabilities that may deposit power not only on the divertor plates but also in the first wall of the main chamber, often in localized areas. The results of this project may help to assess weather fast-ion heat loads to the main chamber first wall due to edge instabilities can pose an additional constraint to the operational regime of a tokamak fusion reactor, or eventually impact its design by the addition of reinforced structures. The experimental results of the project will also be used to benchmark the state-of-the-art codes that the fusion community uses to make projections towards future machines. If successful, the benchmark will strengthen our confidence in our predicting capabilities, while if unsuccessful, the results will motiv
Champ scientifique
Programme(s)
- HORIZON.1.2 - Marie Skłodowska-Curie Actions (MSCA) Main Programme
Régime de financement
HORIZON-TMA-MSCA-PF-EF - HORIZON TMA MSCA Postdoctoral Fellowships - European FellowshipsCoordinateur
41004 Sevilla
Espagne