Pulsed radiofrequency plasma for cleaning ITER first mirrors with and without notch-filter and magnetic field

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-11-11 DOI:10.1016/j.fusengdes.2024.114724
A.M. Dmitriev , A.G. Razdobarin , L.A. Snigirev , D.I. Elets , I.M. Bukreev , E.E. Mukhin , S.Yu. Tolstyakov , I.B. Kupriyanov , L. Moser
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Abstract

In ITER, the first mirrors of optical diagnostics will be prone to deposition of the first wall materials which will result in the degradation of the mirror's optical parameters and the parameters of the diagnostic itself. To restore the mirror's reflectivity a cleaning system based on the gas discharge will be employed. The present paper discussed low-frequency power modulation of capacitively-coupled RF discharge utilized to decrease the mean RF power supplied through the in-vessel feeding line. The impact of power modulation on the incident ion flux, distribution of ion energy, and sputtering rates of the first wall materials were studied for the cases of DC-coupled and -decoupled mirrors with/without external magnetic field. The parameters of the plasma were measured depending on modulation frequency (1 Hz – 10 kHz) and duty cycle (10 – 90 %) for He plasma at a pressure of a few Pa. Based on the measurements of ion flux and ion energy the sputtered rates of Be and BeO were estimated. The estimations of the sputtering rate were followed by experiments on BeO sputtering in He plasma. Finally, the recommendations are given for selecting an appropriate RF power required to clean the mirror from Be/BeO deposits in ITER.
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用于清洁热核聚变实验堆首面反射镜的脉冲射频等离子体(带或不带陷波滤波器和磁场
在热核实验堆中,光学诊断仪的第一面镜子很容易沉积第一壁材料,导致镜子的光学参数和诊断仪本身的参数降低。为了恢复反射镜的反射率,将采用基于气体放电的清洁系统。本文讨论了利用电容耦合射频放电的低频功率调制来降低通过容器内馈电线提供的平均射频功率。针对有/无外部磁场的直流耦合镜和去耦合镜,研究了功率调制对入射离子通量、离子能量分布和第一壁材料溅射率的影响。根据调制频率(1 Hz - 10 kHz)和占空比(10 - 90 %),在几帕压力下测量了 He 等离子体的参数。根据离子通量和离子能量的测量结果,估算出 Be 和 BeO 的溅射率。在对溅射率进行估算之后,还对 He 等离子体中的 BeO 溅射进行了实验。最后,就选择适当的射频功率以清除热核实验堆中反射镜上的铍/氧化铍沉积物提出了建议。
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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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