Measurements of microwave transmission mode in HL-3 tokamak relevant ECH corrugated waveguides transmission line

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-09-29 DOI:10.1016/j.fusengdes.2024.114677
Guoyao Fan , Mei Huang , Donghui Xia , Cheng Chen , Feng Zhang , Xixuan Chen , Wanxin Zheng , Gangyu Chen
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Abstract

The transmission modes of high-power millimeter wave in corrugated waveguides transmission line (TL) are crucial, especially for the long-pulse operation for long-distance TL. The microwave transmission mode in the TL on HL-3 tokamak relevant the electron cyclotron heating system are studied for the purpose according to the phase retrieval method based on intensity distribution measured by an infrared camera at several different locations away from the outlet of TL. A specific high power test platform with about 40-meter TL is established and the mode contents in the middle and the end of the TL are analyzed. In the middle of the TL, the proportion of main transmission mode LP01 mode is about 97 % and other high-order modes contents are <3 %. In the end of the TL, the main mode purity is about 94 %, and the high-order mode, LP11 even mode is excited about 4.6 %. These mode analysis results indicate that the high-power and long-pulse millimeter wave corrugated waveguides TL are designed and machined well, and the alignment method for long distance transmission line installation is highly useful for high-purity wave mode transmission.
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测量 HL-3 托卡马克中与 ECH 波纹波导传输线相关的微波传输模式
高功率毫米波在波纹波导传输线(TL)中的传输模式至关重要,特别是对于长距离TL的长脉冲操作。为此,我们根据红外摄像机在距离传输线出口的几个不同位置测得的强度分布,采用相位检索法研究了与电子回旋加速器加热系统相关的 HL-3 托卡马克传输线中的微波传输模式。建立了一个特定的高功率测试平台,其 TL 长约 40 米,分析了 TL 中部和末端的模式内容。在 TL 中部,主传输模式 LP01 模式所占比例约为 97%,其他高阶模式所占比例为 3%。在 TL 末端,主模式的纯度约为 94%,高阶模式 LP11 偶模式的兴奋度约为 4.6%。这些模态分析结果表明,大功率和长脉冲毫米波波纹波导 TL 的设计和加工性能良好,长距离传输线安装的走线方法对高纯度波模传输非常有用。
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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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