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Preliminary design of the ITER ECH Upper Launcher

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Design Progress of Structural Components of the EU DEMO EC Equatorial Launcher

Jean-Philippe Hogge, René Chavan

The EU DEMO Tokamak is foreseen to be equipped with an electron cyclotron (EC) system for plasma heating, magnetohydrodynamic (MHD) control, and thermal instability suppression. Up to six launchers will be installed into equatorial ports with the aim to in ...

Piscataway2024

High power mm-wave loss measurements of ITER ex-vessel waveguide components at the FALCON test facility at the Swiss Plasma Center

Timothy Goodman, René Chavan, Anastasia Xydou

Many future fusion devices will rely heavily, if not solely, on electron cyclotron (EC) heating subsystems to provide bulk heating, instability control (neoclassical tearing mode (NTM) stabilization), and thermal instability control. Efficient use of the i ...

E D P SCIENCES2023

Tokamak devices aim to magnetically confine a hydrogen plasma at sufficiently high pressure to achieve net energy production from nuclear fusion of light isotopes. Predictive modeling and optimization is crucial for reliable operation of tokamak reactors, ...

EPFL2023

Integration concept of an Electron Cyclotron System in DEMO

Minh Quang Tran, René Chavan, Hartmut Zohm, Konstantinos Avramidis

The pre-conceptual layout for an electron cyclotron system (ECS) in DEMO is described. The present DEMO ECS considers only equatorial ports for both plasma heating and neoclassical tearing mode (NTM) control. This differs from ITER, where four launchers in ...

ELSEVIER SCIENCE SA2021

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

For the EU DEMO Tokamak, Electron Cyclotron (EC) launching systems for plasma heating and stabilization are under development. Various concepts for the optical system are currently studied of which the Mid Steering Antenna (MSA) with a steering mirror at a ...

Elsevier2020

Towards integrated control of tokamak plasmas: physics-based control of neoclassical tearing modes in the TCV tokamak

Mengdi Kong

Neoclassical tearing modes (NTMs), magnetic islands located at rational

q

surfaces, are an important class of resistive magnetohydrodynamics (MHD) instabilities in tokamak plasmas, with

q

the safety factor. NTMs are one of the main constraints of the a ...

EPFL2020

Nearing final design of the ITER EC H&CD Upper Launcher

Olivier Sauter, Timothy Goodman, René Chavan, Jean-Daniel Landis, Robert Bertizzolo, Matteo Vagnoni, Florian Ramseyer, Emanuele Poli

The ITER ECRH system consists of 24 gyrotrons with up to 24 MW installed millimeter wave heating power at 170 GHz, power supplies, control system, transmission lines, one Equatorial and the four Upper Launchers. With its high frequency and small beam focus ...

ELSEVIER SCIENCE SA2019

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Fusion power is the most significant prospects in the long-term future of energy in the sense that it composes a potentially clean, cheap, and unlimited power source that would substitute the widespread traditional nonrenewable energies, reducing the geogr ...

2019

Realistic multi-machine tokamak profile simulations and numerical ramp-down optimization using the RAPTOR code

Anna Teplukhina

Predictive modelling of plasma profiles is an essential part of ongoing research in tokamak plasmas, required for a successful realization of future fusion reactors. This thesis focuses on upgrading the RAPTOR code to extend the area of its applicability f ...

EPFL2018