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An alternative ECRH front steering launcher for the ITER upper port

Publications associées (33)

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Full-discharge simulation and optimization with the RAPTOR code, from present tokamaks to ITER and DEMO

Simon Van Mulders

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

Developments on actuator management, plasma state reconstruction, and control on ASDEX Upgrade

Olivier Sauter, Federico Alberto Alfredo Felici, Mengdi Kong, Simon Van Mulders, Bernhard Sieglin

In present day tokamaks, the role of the control research is to support the physics experiments and to prepare technologies for future devices such as ITER and DEMO. This paper presents the developments done under the MST1 program collaboration on ASDEX Up ...

ELSEVIER SCIENCE SA2021

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Each of the four ITER Electron Cyclotron Heating Upper Launcher (ECHUL) features eight transmission lines (TLs) that are used to inject 170-GHz microwave power into the plasma at a level of up to 1.31 MW (at the TL diamond window) per line. The millimeter ...

IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC2020

Diamond Window Technology for Electron Cyclotron Heating and Current Drive: State of the Art

Konstantinos Avramidis

Nuclear fusion power plants require electron cyclotron (EC) heating and current drive (H&CD) systems for plasma heating and stabilization. High-power microwave beams between 1 and 2?MW generated by gyrotrons propagate in a dedicated waveguide transmission ...

TAYLOR & FRANCIS INC2019

Non-linear simulations of neoclassical tearing mode control by externally driven RF current and heating, with application to ITER

Fabien Widmer

Neoclassical tearing modes (NTM) must be controlled or suppressed to prevent a degradation of the energy confinement in tokamak plasmas. This can be done applying RF-current via electron cyclotron current drive and -heating at the rational surface where th ...

2019

Status Status of the final design of the EC UPP launcher

René Chavan, Jean-Daniel Landis

Four EC H&CD (Electron Cyclotron Heating and Current Drive) launchers will be installed into the upper ports #12, #13, #15 and #16 in ITER. Beside plasma heating their main purpose is to counteract plasma instabilities by injecting up to 20 MW of microwave ...

ELSEVIER SCIENCE SA2018

A Friction Compensation Control for Power Steering

Philippe Müllhaupt, Robert Fuchs

The effects of friction are critical to the dynamics of electric power steering (EPS). On the one hand, friction contributes to the stability of the system and filters some of the disturbances (road vibration, etc.). On the other hand, it affects negativel ...

Ieee-Inst Electrical Electronics Engineers Inc2015

The four ITER Electron Cyclotron Upper Launchers (UL) are designed to control Magneto-Hydrodynamic instabilities with the deposition of Electron Cyclotron power. According to the present design, each launcher comprises two rows of four input waveguides, wh ...

EDP Sciences2015

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The design of the ITER ECRH system provides 20 MW millimeter wave power for central plasma heating and MHD stabilization. The system consists of an array of 24 gyrotrons with power supplies coupled to a set of transmission lines guiding the beams to the fo ...

Elsevier Science Sa2014