Viezzer, EleonoraBirkenmeier, G.2024-11-262024-11-262024-09-18Oyola Domínguez, P. (2024). Development of advanced numerical Tools for fusion reactor Diagnostics and nonlinear modeling of Plasma Dynamics. (Tesis Doctoral Inédita). Universidad de Sevilla, Sevilla.https://hdl.handle.net/11441/164933A precise control and understanding of the plasma dynamics is crucial for future fusion reactors. The complex dynamics and the harsh environments in magnetic fusion devices, such as tokamaks, require the most advanced modeling techniques both from the theoretical predictive side, to the experiment diagnosis and data analysis. In this PhD thesis, a two-fold approach is presented to advance in the understanding and control of the plasma dynamics. From the experimental side, a novel diagnostic, the imaging Heavy Ion Beam Probe (i-HIBP), has been installed, commissioned and operated at the ASDEX Upgrade tokamak during this thesis. The i-HIBP has been installed in the ASDEX Upgrade tokamak (Germany), in collaboration with the Max-Planck Institute for Plasma Physics. This diagnostic uses heavy alkali as probe ions that, after passing through the plasma, reach a scintillator plate. The footprint on the scintillator encodes information of the plasma density and the electromagnetic perturbations along their trajectories in the plasma. In this work, the modeling tools have been developed and applied to reproduce the signals and extract relevant information on edge plasma density and current density perturbations. In particular, it is shown that even in a low signal-to-noise ratio scenario, the plasma density can be reconstructed at the plasma edge with an excellent radial resolution. On the theoretical and modeling side, this PhD thesis focuses on studying the fast ions(suprathermal particles), as they will play a key role in the fusion power generation: they are envisioned to be the most important source of energy (heating) and momentum. Fast-ion losses can lead to a decrease in the power throughput and, when localized, could potentially damage the first wall components. A renewed interest in an alternative tokamak scenario, based on the negative-triangularity shaped plasma, has arisen the question of the fast-ion confinement and the possible instabilities that they could suffer. In this work, this topic is addressed by using one of the most advanced hybrid kinetic magnetohydrodynamics codes in the community, the MEGA code, to study the behavior and transport of a Toroidal Alfvén Eigenmode (TAE). The results presented here show that the confinement of the fast-ions is more resilientapplication/pdf152 p.engAttribution-NonCommercial-NoDerivatives 4.0 Internationalhttp://creativecommons.org/licenses/by-nc-nd/4.0/Development of advanced numerical Tools for fusion reactor Diagnostics and nonlinear modeling of Plasma Dynamicsinfo:eu-repo/semantics/doctoralThesisinfo:eu-repo/semantics/embargoedAccess