Design of a 170GHz quasi-optical notch filter for microwave-based diagnostics protection on the burning plasma device

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2025-03-04 DOI:10.1016/j.fusengdes.2025.114925
Chen Luo , Xiaopin Tang , Calvin Domier , Xiaoliang Li , Ang Ti , Pengjun Sun , Shasha Qiu , Xinhang Xu , Xianzi Liu , Yilun Zhu , Neville Luhmann
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引用次数: 0

Abstract

170 GHz gyrotrons will be used for Electron Cyclotron Heating (ECH) on the under-development burning plasma device, with a maximum power output of 16 MW with center frequency of 170 GHz. The reliable 170 GHz quasi-optical notch filters protect microwave-based diagnostic instruments from unabsorbed ECH power. This design utilizes a metal circular periodic structure, which is straightforward to manufacture, to achieve reflection and absorption of 170 GHz electromagnetic waves transmitted through space, thereby achieving the notch filtering effect (attenuation > 60 dB). Unlike the rectangular ring design used in low-frequency quasi-optical notch filters, the circular design caters to the shorter wavelength of 170 GHz, which necessitates reduced fabrication error tolerance. To achieve both high quality filter and higher processing yields, we compensate for the performance degradation of the notch filter caused by processing errors by optimizing the controllable metal circle radius and incident angle. This paper discusses the impact of material size selection and machining accuracy deviations on the performance of the notch filter.
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设计用于燃烧等离子体装置微波诊断保护的 170GHz 准光学陷波滤波器
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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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