Recent progress of the ECRH system and initial experimental results on the J-TEXT tokamak

托卡马克 回旋管 电子回旋共振 回旋加速器 等离子体 轴向对称偏滤器实验 原子物理学 韧致辐射 电子 物理 温度电子 核物理学 材料科学 核工程 工程类
作者
Donghui Xia,Xixuan Chen,Dengfeng Xu,Jiangang Fang,Junli ZHANG,Nengchao Wang,Zhoujun Yang,Zhongyong Chen,Yonghua Ding,Wei Zheng,Shaoxiang Ma,Zhijiang Wang,Yuan Pan
出处
期刊:Plasma Science & Technology [IOP Publishing]
卷期号:24 (12): 124010-124010 被引量:6
标识
DOI:10.1088/2058-6272/aca4b5
摘要

Abstract In order to broaden the range of the plasma parameters and provide experimental conditions for physical research into high-performance plasma, the development of the electron cyclotron resonance heating (ECRH) system for the J-TEXT tokamak was initiated in 2017. For the first stage, the ECRH system operated successfully with one 105 GHz/500 kW/1 s gyrotron in 2019. More than 400 kW electron cyclotron (EC) wave power has been injected into the plasma successfully, raising the core electron temperature to 1.5 keV. In 2022, another 105 GHz/500 kW/1 s gyrotron completed commissioning tests which signifies that the ECRH system could generate an EC wave power of 1 MW in total. Under the support of the ECRH system, various physical experiments have been carried out on J-TEXT. The electron thermal transport in ECRH plasmas has been investigated. When ECRH is turned on, the electron thermal diffusivity significantly increases. The runaway current is elevated when a disruption occurs during ECRH heating. When the injected EC wave power is 400 kW, the conversion efficiency of runaway current increases from 35% to 75%. Fast electron behavior is observed in electron cyclotron current drive (ECCD) plasma by the fast electron bremsstrahlung diagnostic (FEB). The increase in the FEB intensity implies that ECCD could generate fast electrons. A successful startup with a 200 kW ECW is achieved. With the upgrade of the ECRH system, the J-TEXT operational range could be expanded and further relevant research could be conducted.

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