Study of runaway electrons during EAST plasma start-up

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

Fusion Engineering and Design Pub Date : 2025-06-06 DOI:10.1016/j.fusengdes.2025.115232

Y. Hong , L. Zeng , T. Tang , D.L. Chen , S.Y. Lin , H.L. Zhao , T.F. Zhou , A. Ti , C.X. Lou , W. Xia , H.Q. Liu , J.P. Qian , X. Gao

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Abstract

Herein, the generation and loss of runaway electrons (REs) during the plasma start-up phase are observed in the Experimental Advanced Superconducting Tokamak (EAST). A dataset of nearly 400 ohmic discharges is established, and statistical analysis is employed to investigate the relationship between RE generation and key plasma parameters. It is observed that generation of REs is considerably suppressed under conditions of high plasma density and low loop voltage. REs are detected to be considerably in number when the ratio of the loop electric field to critical electric field, E_loop/E_c exceed 10 during the start-up phase. In addition, analysis of the correlation between plasma streaming parameters and E_loop/E_c reveals that a substantial population of REs is generated when electron temperature exceeds 700 eV. Moreover, a sudden drop in plasma current is observed to be consistent with the loss of REs, which is primarily due to macroscopic magnetohydrodynamics.

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EAST等离子体启动过程中失控电子的研究

本文在实验先进超导托卡马克（EAST）中观察了等离子体启动阶段失控电子（REs）的产生和损失。建立了近400次欧姆放电数据集，利用统计分析方法研究了等离子体关键参数与RE生成的关系。观察到，在高等离子体密度和低环路电压条件下，REs的产生明显受到抑制。在启动阶段，当回路电场与临界电场Eloop/Ec之比超过10时，REs的数量就会相当大。此外，等离子体流化参数与Eloop/Ec之间的相关性分析表明，当电子温度超过700 eV时，会产生大量的REs。此外，观察到等离子体电流的突然下降与REs的损失是一致的，这主要是由于宏观磁流体动力学。

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.