Preliminary results and analysis of a tangential TV Thomson scattering diagnostic system on EAST

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-10-29 DOI:10.1016/j.fusengdes.2024.114696

Y.X. Zhu , Q. Zang , W. Chu , M․Yu Kantor , G.L. Lin , M.F. Ren

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Abstract

This paper presents the latest development of a tangential TVTS (Television Thomson scattering) system on the EAST Tokamak and the preliminary results obtained recently. For the goals of the thousand-second H-mode on EAST, it is obviously essential for the experimental operation and physical research to develop a high spatial resolution edge Thomson scattering diagnostic system. The new system uses a tangential optical path, mainly covering plasma ρ = 0.8 – 1.1 region. A high energy 532 nm laser was designed as the light source, which can realize the stable output of 10 Hz/3.5 J in the time of a thousand seconds through the new optical structure technology. In order to improve the scattering light splitting efficiency, the transmission grating is used as the main splitting device. We use a three-step image enhancement amplification technique so that the detection efficiency of the system can reach 3000 counts/photon. At present, the spatial resolution of the system is about 3 mm, and the measurement electron temperature (T_e) range is 50 eV - 2 keV, the electron temperature error is expected <7 %.

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EAST 上切向电视汤姆逊散射诊断系统的初步结果和分析

本文介绍在EAST托卡马克上开发切向TVTS（电视汤姆逊散射）系统的最新情况以及最近取得的初步成果。为了在EAST上实现千秒级H模式的目标，开发一个高空间分辨率的边缘汤姆逊散射诊断系统对于实验运行和物理研究显然是至关重要的。新系统采用切向光路，主要覆盖等离子体 ρ = 0.8 - 1.1 区域。光源采用高能量 532 nm 激光器，通过新型光学结构技术，可在千秒时间内实现 10 Hz/3.5 J 的稳定输出。为了提高散射光的分光效率，我们采用了透射光栅作为主要分光器件。我们采用三步图像增强放大技术，使系统的探测效率达到 3000 计数/光子。目前，该系统的空间分辨率约为 3 毫米，测量电子温度（Te）范围为 50 eV - 2 keV，电子温度误差预计为 7%。

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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.