An automatic matching system for the ICRF antenna at TOMAS: Development and experimental proof

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
A. Adriaens , F. Durodié , V. Maquet , S. Deshpande , D. López-Rodríguez , M. Verstraeten , A. Goriaev , K. Crombé , J. Buermans , S. Brezinsek
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引用次数: 0

Abstract

The TOMAS device is equipped with an Ion Cyclotron Range-of-Frequency (ICRF) system enabling systematic investigations of Ion Cyclotron Wall Conditioning (ICWC) in a toroidal geometry complementing plasma-wall interaction and plasma production research in larger devices.
The ICRF system on the TOMAS device has a varying load as the plasma may change in density, pressure, magnetic field and species (H/D/He/Ar) depending on the required experimental conditions. Therefore, a T-matching capacitor network is installed. To correctly control these variable capacitors in order to achieve efficient power transmission to the plasma, in this paper, multiple algorithms were developed. The first kind of algorithm requires voltage probes along a coaxial line connecting the power source to the antenna, for these kinds algorithms at least 4 inputs are necessary: at least 3 voltage probe measurements along the line and the amplitude of the forward voltage, either measured directly or inferred using the requested power gain. For the second form of algorithm the amplitude of both the forward and reflected wave need to be measured as well as their phase difference. System parameters were investigated over the course of simulations and afterwards tests of one of the algorithms were carried out on the TOMAS machine, confirming its effectiveness.
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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