期刊论文

Yin, X.;Zhang, H.

中文

核技术

0253-3219

2022

45

3

59-66

10.11889/j.0253-3219.2022.hjs.45.030501

国家重点研发计划磁约束聚变能源研究专项(No.2017YFE0301300、No.2018YFE0301 100 、No.2019YFE03030002、No.2018YFE0303103)、 国家自然科学基金(No.1 1805231 )、安徽省重点研究与开发计划项目(No.202104a06020021)、安徽省自然科学基金(No.1908085J01、No. 2008085QA39)、中科院等离子体物理研究所科学基金(No.DSJJ-202002)、磁约束聚变安徽省实验室开放基金项目(No.2021AMF01002)、安 徽高校协同创新项目(No.GXXT -2021-029) 第一作者：计华健，男，1996年出生，2018年毕业于安徽工业大学，硕士研究生，主要从事等离子体光谱诊断和等离子体物理研究 通信作者：张洪明，E-mail：hmzhang@ipp.ac.cn；尹相辉，E-mail：yinxh@usc.edu.cn 收稿日期：2021-1 1-05，修回日期：2022-01-05 Supported by National Magnetic Confinement Fusion Science Program of China (No. 2017YFE0301300, No. 2018YFE0301 100 , No. 2019YFE03030002, No.2018YFE0303103), National Natural Science Foundation of China (No.1 1805231 ), Key Research and Development Projects of Anhui Province (No.202104a06020021), Anhui Provincial Natural Science Foundation (No.1908085J01, No.2008085QA39), ASIPP Science Fund (No.DSJJ-202002), Open Fund of Magnetic Confinement Fusion Laboratory of Anhui Province (No.2021AMF01002), the University Synergy Innovation Program of Anhui Province (No.GXXT -2021-029) First author: JI Huajian, male, born in 1996, graduated from Anhui University of T echnology spectroscopicdiagnosisandplasmaphysicsresearch Corresponding author: ZHANG Hongming, E-mail: hmzhang@ipp.ac.cn; YIN Xianghui, E-mail: yinxh@usc.edu.cn Received date: 2021-1 1-05, revised date: 2022-01-05

本校为第一机构

通过在偏滤器区域充入适量氖气(Ne)或氩气(Ar),东方超环(Experimental Advanced Super-conducting Tokamak,EAST)托卡马克装置实现了辐射偏滤器运行模式。在辐射偏滤器运行模式下,靶板热负荷显著降低,有效缓解了高能粒子流对偏滤器靶板的损伤。但是在偏滤器区域充入过量杂质气体时,杂质粒子会沿着磁力线进入主等离子体,影响主等离子体的约束性能,甚至导致等离子体破裂。因此,有必要研究偏滤器区域等离子体杂质浓度的估算方法,分析充入杂质气体时该区域杂质的定量变化,以此来评估充入的杂质气体对芯部等离子体约束性能的影响。本文针对不同的杂质种类,建立了不同的杂质浓度估算方法。对于钨杂质,...

Background: By injecting gaseous neon (Ne) or argon (Ar) into the divertor region, the radiative divertor operation mode has been successfully realized on experimental advanced superconducting tokamak (EAST). During the radiative divertor operation phase, the damage to divertor plates is effectively mitigated by reducing heat load from high energy particles. However, the injected excess impurity gas may penetrate the last closed flux surface and transport to the core region, causing the degradation of core plasma confinement. Purpose: This stud...