Mirror dual cleaning of ITER equatorial diagnostic Wide Angle Viewing System

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2025-03-01 DOI:10.1016/j.fusengdes.2025.114892
L. Marot , P. Hiret , S. Dine , A. Dmitriev , L. Letellier , S. Vives , F. Le Guern , J. Piqueras , M. Martina , R. Steiner , R. Maffiolini , A. Tonin , E. Meyer
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Abstract

The metallic first mirrors (FMs) are expected to play a crucial role in most optical diagnostic systems in the International Thermonuclear Experimental Reactor (ITER). However, these mirrors will be subjected to deposition of the first-wall materials, which will comprise their optical properties. Thus, the FMs will require periodic cleaning to restore their optical properties, which is anticipated to be achieved using an in situ plasma cleaning technique employing radio-frequency (RF) discharges. The left tangential line of sight of the Wide Angle Viewing System (WAVS) for the ITER Equatorial Port 12 FM unit, designed by CEA Cadarache, was simplified and manufactured at the University of Basel for RF-cleaning tests in a realistic geometry. Plasma ignition on mirrors M1 and M2 was achieved at a frequency of 13.56 MHz. Both mirrors were successfully cleaned with a 20-nm aluminum oxide (Al2O3) film replicating a contaminant layer. However, powering M1 and M2 in a dual cleaning regime with argon atmosphere at 1 Pa with 100 W of RF power for 1h and 45min (with a −300 V self-bias) allowed for the simultaneous removal of the Al2O3 layer from the rhodium mirror insets on both mirrors. The temperature of the mineral insulating (MI) cables used for powering the first mirror remained well below the maximum rated temperature. A cleaning demonstration was also performed on a stratified mirror prototype developed by CEA. The effectiveness of the dual cleaning technique for the Equatorial Port 12 WAVS diagnostic was validated by powering both FMs in a direct-current (DC) coupled regime, as all reported diagnostics will use a DC decoupled mode.
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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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