Neutral beam attenuation in the HL-3 Tokamak: simulation and experimental analysis of BES diagnostic performance

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-09-10 DOI:10.1016/j.fusengdes.2025.115419

X.Q. Yang , Y. Yu , C.Y. Xiao , R. Ke , S.B. Gong , R. Jin , W.W. Cheng , S.J. Zhu , Z.B. Wang , J. Chen , M. Xu

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引用次数: 0

Abstract

Neutral beam (NB) attenuation represents a critical factor for evaluating energy deposition in tokamaks, offering essential references both for plasma discharge operations and for plasma density diagnostics. This study theoretically calculates NB attenuation coefficients and Doppler shifted Balmer Dα photon flux levels for the newly installed 32-channel Beam Emission Spectroscopy (BES) system on the HL-3 tokamak, utilizing the ADAS (Atomic Data and Analysis Structure) database with actual NB injection parameters and plasma profile data. The calculation methodology is validated through experimental comparisons with BES-measured photon flux profiles. Simulation results demonstrate adequate line intensity for proposed 128-channel BES implementation under typical HL-3 operating conditions characterized by elevated plasma densities and electron temperatures. This analytical approach enables direct evaluation of NB energy deposition via attenuation coefficients or photon flux peak analysis, providing rapid assessment of NBI heating efficiency during shot-to-shot intervals. Furthermore, this work highlights BES diagnostics' significant potential for optimizing heating efficiency and plasma current drive performance.

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HL-3托卡马克中性束衰减：BES诊断性能的仿真与实验分析

中性束（NB）衰减是评估托卡马克能量沉积的关键因素，为等离子体放电操作和等离子体密度诊断提供了重要参考。本文利用ADAS （Atomic Data and Analysis Structure）数据库中实际NB注入参数和等离子体剖面数据，对HL-3托卡马克上新安装的32通道束流发射光谱（BES）系统的NB衰减系数和多普勒频移Balmer Dα光子通量水平进行了理论计算。通过与bes测量的光子通量曲线的实验比较，验证了计算方法的正确性。仿真结果表明，在等离子体密度和电子温度升高的典型HL-3操作条件下，线路强度足以实现128通道BES。这种分析方法可以通过衰减系数或光子通量峰分析直接评估NB能量沉积，在弹间间隔内快速评估NBI加热效率。此外，这项工作强调了BES诊断在优化加热效率和等离子体电流驱动性能方面的巨大潜力。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.