Modeling of divertor power footprint widths on EAST by SOLPS5.0/B2.5-Eirene

The edge plasma code package SOLPS5.0 is employed to simulate the divertor power footprint widths of the experimental advanced superconducting tokamak （EAST） L-mode and ELM-free H-mode plasmas.The divertor power footprint widths,which consist of the scrape-off layer （SOL） width λq and heat spreading...

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Published inPlasma science & technology Vol. 19; no. 4; pp. 28 - 33
Main Author 邓国忠 刘晓菊 王亮 刘少承 许吉禅 冯威 刘建斌 刘欢 高翔
Format Journal Article
LanguageEnglish
Published IOP Publishing 01.04.2017
Subjects
divertor power footprint widths
plasma current
SOLPS
偏滤器
反应堆功率
宽度
建模
托卡马克实验装置
托卡马克聚变装置
等离子体电流
等离子体边缘
Online AccessGet full text
ISSN1009-0630
1009-0630
DOI10.1088/2058-6272/aa5802

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Summary:The edge plasma code package SOLPS5.0 is employed to simulate the divertor power footprint widths of the experimental advanced superconducting tokamak （EAST） L-mode and ELM-free H-mode plasmas.The divertor power footprint widths,which consist of the scrape-off layer （SOL） width λq and heat spreading S,are important physical parameters for edge plasmas.In this work,a plasma current scan is implemented in the simulation to obtain the dependence of the divertor power footprint width on the plasma current Ip.Strong inverse scaling of the SOL width with Ip has been achieved for both L-mode and H-mode plasmas in the forms of λq,L-mode =4.98 × Ip-0.68 and λq,H-mode =1.86 × Ip-1.08.Similar trends have also been demonstrated in the study of heat spreading with SL-mode =1.95 × Ip-0.542 and SH-mode =0.756 × Ip-0.872.In addition,studies on divertor peak heat load and the magnetic flux expansion factor show that both of them are proportional to plasma current.The simulation work here can act as a way to explore the power footprint widths of future tokamak fusion devices such as ITER and the China Fusion Engineering Test Reactor （CFETR）.
Bibliography:Guozhong DENG1,2, Xiaoju LIU1, Liang WANG1, Shaocheng LIU1, Jichan XU1, Wei FENG1, Jianbin LIU1, Huan LIU1 and Xiang GAO1,2（1 Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, People＇s Republic of China 2University of Science and Technology of China, Hefei 230026, People＇s Republic of China）
The edge plasma code package SOLPS5.0 is employed to simulate the divertor power footprint widths of the experimental advanced superconducting tokamak （EAST） L-mode and ELM-free H-mode plasmas.The divertor power footprint widths,which consist of the scrape-off layer （SOL） width λq and heat spreading S,are important physical parameters for edge plasmas.In this work,a plasma current scan is implemented in the simulation to obtain the dependence of the divertor power footprint width on the plasma current Ip.Strong inverse scaling of the SOL width with Ip has been achieved for both L-mode and H-mode plasmas in the forms of λq,L-mode =4.98 × Ip-0.68 and λq,H-mode =1.86 × Ip-1.08.Similar trends have also been demonstrated in the study of heat spreading with SL-mode =1.95 × Ip-0.542 and SH-mode =0.756 × Ip-0.872.In addition,studies on divertor peak heat load and the magnetic flux expansion factor show that both of them are proportional to plasma current.The simulation work here can act as a way to explore the power footprint widths of future tokamak fusion devices such as ITER and the China Fusion Engineering Test Reactor （CFETR）.
divertor power footprint widths, plasma current, SOLPS
34-1187/TL
Institute of Plasma Physics
PST-2016-0285.R3
ISSN:1009-0630
1009-0630
DOI:10.1088/2058-6272/aa5802