Feasibility study of the high-power millimeter-wave collective Thomson scattering diagnostic system on HL-3 tokamak

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-06-09 DOI:10.1016/j.fusengdes.2025.115242

Feng Zhang, Mei Huang, Gangyu Chen, Wanxin Zheng, Cheng Chen, Guoyao Fan, He Wang

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引用次数: 0

Abstract

Collective Thomson scattering (CTS) is an important diagnostic technique which can be applied to measure the velocity distribution of fast ions within fusion plasmas with high temporal and spatial resolutions. The feasibility of diagnosing fast ions in the HL-3 tokamak by high-power millimeter-wave CTS was studied. Specifically, the study examined the effects of various factors, including the frequency of the probing wave, scattering geometry and plasma parameters, on the scattering spectrum. Among the various plasma parameters, this study specifically focused its analysis on the effects of electron density, electron temperature, bulk ion temperature, and fast ion density on the scattering spectrum and, consequently, on the inference of the fast ion distribution. Finally, a CTS diagnostic system for the HL-3 tokamak was designed. In this setup, the 140 GHz and 1 MW gyrotron served as the probe beam source, the diagnostic system could achieve temporal and spatial resolutions of approximately 200 µs and 100 mm, respectively.

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HL-3托卡马克上大功率毫米波集体汤姆逊散射诊断系统的可行性研究

集体汤姆逊散射（CTS）是一种重要的诊断技术，可用于测量聚变等离子体内快离子的速度分布，具有较高的时空分辨率。研究了高功率毫米波CTS在HL-3托卡马克中诊断快离子的可行性。具体而言，研究考察了探测波频率、散射几何形状和等离子体参数等因素对散射谱的影响。在各种等离子体参数中，本研究重点分析了电子密度、电子温度、体离子温度和快离子密度对散射谱的影响，从而推断出快离子的分布。最后，设计了HL-3托卡马克的CTS诊断系统。采用140 GHz和1 MW回旋管作为探测波源，诊断系统的时间和空间分辨率分别约为200µs和100 mm。

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来源期刊

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.