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Turbulence and flows in the plasma boundary of snowflake magnetic configurations

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Understanding the turbulent dynamics in the outermost region of the tokamak is essential to predict and control the heat and particle loads to the vessel wall, a crucial problem for the entire fusion program. In this thesis, the problem is approached via t ...

EPFL2021

Model-based optimization of magnetic control in the TCV tokamak: design and experiments

Federico Pesamosca

Thermonuclear controlled fusion is a promising answer to the current energy and climate issues, providing a safe carbon-free source of energy which is virtually inexhaustible. In magnetic confinement thermonuclear fusion based on tokamak reactors, hydrogen ...

EPFL2021

Development of an 11-channel multi wavelength imaging diagnostic for divertor plasmas in MAST Upgrade

Basil Duval, Yanis Andrebe, Artur Perek, Wouter Vijvers

Divertor detachment and alternative divertor magnetic geometries are predicted to be promising approaches to handle the power exhaust of future fusion devices. In order to understand the detachment process caused by volumetric losses in alternative diverto ...

AMER INST PHYSICS2021

Local gyrokinetic simulations use a field-aligned domain that twists due to the magnetic shear of the background magnetic equilibrium. However, if the magnetic shear is strong and/or the domain is long, the twist can become so extreme that it fails to prop ...

2021

Investigating Scrape-Off Layer transport in alternative divertor geometries on the TCV tokamak

Roberto Maurizio

Thermonuclear fusion is a potentially clean and limitless energy source that can substantially change the current global electricity generation mix, which is highly dependent on limited fossil fuels. This thesis contributes to the development of fusion en ...

EPFL2020

Assessment of alternative divertor configurations as an exhaust solution for DEMO

Holger Reimerdes, Roberto Maurizio, Seungkyu Ha, Hartmut Zohm

Plasma exhaust has been identified as a major challenge towards the realisation of magnetic confinement fusion. To mitigate the risk that the single null divertor (SND) with a high radiation fraction in the scrape-of-layer (SOL) adopted for ITER will not e ...

2020

Quench analysis of the DEMO CS1 coil

Kamil Sedlák

The European DEMOnstration Fusion Power Plant (EU-DEMO) is being designed as an intermediary stage between the ITER experimental reactor and future commercial fusion power plants. The EU-DEMO is based on the tokamak concept with a fully superconducting mag ...

ELSEVIER SCI LTD2020

Inter-Layer Joint of Nb3Sn React&Wind Cables for Fusion Magnets

Pierluigi Bruzzone, Kamil Sedlák, Boris Stepanov, Vincenzo D'Auria

The Swiss Plasma Center (SPC) has developed a layout of Toroidal Field (TF) coil for EUROfusion DEMO tokamak, based on the reference tokamak baseline of 2015. Each TF coil winding pack is wound with graded Nb3Sn conductors and consists of 12 single layers, ...

IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC2020

The 1-dimensional reaction-diffusion-convection code TOMATOR-1D describes plasma production by RF waves inside a tokamak using the Braginskii continuity and heat balance equations. The model simulates self-consistent radial density and temperature profiles ...

2020

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Results of 3D, flux-driven, global, two-fluid turbulence simulations are presented for the first time in snowflake (SF) configurations, including the ideal SF, SF plus and SF minus configurations. The analysis is focused on the distribution of the heat flu ...

2020