Influence of the X-point location on edge plasma transport in the J-TEXT tokamak with a high-field-side single-null divertor

Hao WANG (王灏); Yunfeng LIANG (梁云峰); Shuai XU (徐帅); Zhonghe JIANG (江中和); Yuhe FENG (冯玉和); A KNIEPS; P DREWS; Jie YANG (阳杰); Xin XU (徐鑫); Ting LONG (龙婷)

doi:10.1088/2058-6272/ac224a

Plasma Science and Technology > 2021 > 23(12): 125103. > DOI: 10.1088/2058-6272/ac224a

Hao WANG (王灏), Yunfeng LIANG (梁云峰), Shuai XU (徐帅), Zhonghe JIANG (江中和), Yuhe FENG (冯玉和), A KNIEPS, P DREWS, Jie YANG (阳杰), Xin XU (徐鑫), Ting LONG (龙婷). Influence of the X-point location on edge plasma transport in the J-TEXT tokamak with a high-field-side single-null divertor[J]. Plasma Science and Technology, 2021, 23(12): 125103. DOI: 10.1088/2058-6272/ac224a

Citation:

PDF (3649 KB)

Influence of the X-point location on edge plasma transport in the J-TEXT tokamak with a high-field-side single-null divertor

¹ International Joint Research Laboratory of Magnetic Confinement Fusion and Plasma Physics, State Key Laboratory of Advanced Electromagnetic Engineering and Technology, School of Electrical and Electronic Engineering, Huazhong University of Science and Technology, Wuhan 430074, People's Republic of China
² Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung-Plasmaphysik, Partner of the Trilateral Euregio Cluster (TEC), 52425 Jülich, Germany
³ Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, People's Republic of China
⁴ Max-Planck-Institut fur Plasmaphysik, EURATOM Association, 17491 Greifswald, Germany
⁵ Southwestern Institute of Physics, Chengdu 610041, People's Republic of China
⁶ Advanced Energy Research Center, Shenzhen University, Shenzhen 518060, People's Republic of China

Funds: his work is supported by the National Magnetic Confinement Fusion Energy R&D Program of China (Nos. 2018YFE0301104 and 2018YFE0309100), and National Natural Science Foundation of China (No. 51821005).

More Information

Received Date: June 08, 2021
Revised Date: August 28, 2021
Accepted Date: August 29, 2021

Graphical Abstract

Abstract

Abstract

High-density experiments in the high-field-side mid-plane single-null divertor configuration have been performed for the first time on J-TEXT. The experiments show an increase in the highest central channel line-averaged density from $2.73\,\times \,{10}^{19}\,{{\rm{m}}}^{-3}$ to $6.49\,\times \,{10}^{19}\,{{\rm{m}}}^{-3}$ , while the X-point moves away from the target by increasing the divertor coil current. The corresponding Greenwald fraction rises from 0.50 to 0.79. For the impurity transport, the density normalized radiation intensity (absolute extreme ultraviolet and soft x-ray) of the central channel density decreased significantly (>50%) with an increase in the plasma density. To better understand the underlying physics mechanisms, the 3D edge Monte Carlo code coupled with EIRENE (EMC3- EIRENE) has been implemented for the first time on J-TEXT. The simulation results show good agreement with the experimental findings. As the X-point moves away from the target, the divertor power decay length drops and the scrape-off layer impurity screening effect is enhanced.
- edge plasma transport,
- divertor configuration,
- EMC3-EIRENE

FullText(HTML)

References (48)

References

[1]	Pitcher C S and Stangeby P C 1997 Plasma Phys. Control.Fusion 39 779
[2]	Guo H Y et al 2019 Nucl. Fusion 59 086054
[3]	Ryutov D D and Soukhanovskii V A 2015 Phys. Plasmas 22 110901
[4]	Ohyabu N et al 1994 Nucl. Fusion 34 387
[5]	Strumberger E 1996 Nucl. Fusion 36 891
[6]	Kukushkin A S et al 2011 Fusion Eng. Des. 86 2865
[7]	Stangeby P C 2000 The Plasma Boundary of Magnetic Fusion Devices (Boca Raton, FL: CRC Press)
[8]	Lackner K and Keilhacker M 1984 J. Nucl. Mater.128–129 368
[9]	Wischmeier M et al 2009 J. Nucl. Mater. 390–391 250
[10]	Matthews G F 1995 J. Nucl. Mater. 220–222 104
[11]	Zhang M et al 2015 J. Fusion Energy 34 509
[12]	Liang Y et al 2019 Nucl. Fusion 59 112016
[13]	Chen Z P 2021 Realization of divertor configuration discharge in J-TEXT tokamak Proceedings of the 28th IAEA Fusion Energy Conference (Vienna) (IAEA)
[14]	Feng Y et al 1997 J. Nucl. Mater. 241–243 930
[15]	Feng Y et al 2004 Contrib. Plasma Phys. 44 57
[16]	Feng Y et al 2013 Comput. Phys. Commun. 184 1555
[17]	Kobayashi M et al 2014 Contrib. Plasma Phys. 54 383
[18]	Feng Y et al 2014 Contrib. Plasma Phys. 54 426
[19]	Schneider R et al 1992 J. Nucl. Mater. 196 810
[20]	Reiter D, Baelmans M and Börner P 2005 Fusion Sci. Technol.47 172
[21]	Zhang X L et al 2014 Rev. Sci. Instrum. 85 11E420
[22]	Li J C et al 2014 Rev. Sci. Instrum. 85 11E414
[23]	Chen J et al 2012 Rev. Sci. Instrum. 83 10E306
[24]	Long T et al 2020 Rev. Sci. Instrum. 91 083504
[25]	Lao L L et al 1985 Nucl. Fusion 25 1611
[26]	Greenwald M et al 1988 Nucl. Fusion 28 2199
[27]	Effenberg F et al 2017 Nucl. Fusion 57 036021
[28]	Kawamura G et al 2014 Contrib. Plasma Phys. 54 437
[29]	Kawamura G et al 2018 Plasma Phys. Control. Fusion 60 084005
[30]	Dai S Y et al 2018 Nucl. Fusion 58 096024
[31]	Oishi T et al 2018 Nucl. Fusion 58 016040
[32]	Dai S Y et al 2016 Nucl. Fusion 56 066005
[33]	Kobayash M et al 2004 Contrib. Plasma Phys. 44 25
[34]	Frerichs H et al 2010 Nucl. Fusion 50 034004
[35]	Lunt T et al 2012 Nucl. Fusion 52 054013
[36]	Harting D et al 2011 J. Nucl. Mater. 415 S540
[37]	Lunt T et al 2014 Plasma Phys. Control. Fusion 56 035009
[38]	Huang J et al 2014 Plasma Phys. Control. Fusion 56 075023
[39]	Dai S Y et al 2021 Plasma Phys. Control. Fusion 63 025003
[40]	Dai S Y et al 2020 J. Plasma Phys. 86 815860303
[41]	Liu B et al 2020 Plasma Phys. Control. Fusion 62 035003
[42]	Xie T et al 2018 Nucl. Fusion 58 106017
[43]	Xu S et al 2018 Nucl. Fusion 58 106008
[44]	Xu S et al 2020 Nucl. Fusion 60 056006
[45]	https://adas.ac.uk/
[46]	Liang Z et al 2021 Phys. Scr. 96 065601
[47]	Feng Y et al 2009 Nucl. Fusion 49 095002
[48]	Zhao Q et al 2021 IEEE 4th International Electrical and Energy Conference (https://doi.org/10.1109/CIEEC50170.2021.9510443)

[1]	Zhipeng CHEN, Lizhi ZHU, Xin XU, Wei ZHENG, Ming ZHANG, Li GAO, Minghui XIA, Jie YANG, Mingchong ZHU, Zhigang HAO, Shaodong JIAO, Zhifeng CHENG, Zhoujun YANG, Xiaoqing ZHANG, Zhongyong CHEN, Nengchao WANG, Yonghua DING, Ge ZHUANG, Kenneth W GENTLE, Yunfeng LIANG, Yuan PAN, the J-TEXT Team. Realization of divertor configuration discharge in J-TEXT tokamak[J]. Plasma Science and Technology, 2022, 24(12): 124008. DOI: 10.1088/2058-6272/aca0dc
[2]	J COSFELD, P DREWS, B BLACKWELL, M JAKUBOWSKI, H NIEMANN, D ZHANG, Y FENG, the Wendelstein -X Team. Numerical estimate of multi-species ion sound speed of Langmuir probe interpretations in the edge plasmas of Wendelstein 7-X[J]. Plasma Science and Technology, 2020, 22(8): 85102-085102. DOI: 10.1088/2058-6272/ab8974
[3]	Kristel GHOOS, Heinke FRERICHS, Wouter DEKEYSER, Giovanni SAMAEY, Martine BAELMANS. Numerical accuracy and convergence with EMC3-EIRENE[J]. Plasma Science and Technology, 2020, 22(5): 54001-054001. DOI: 10.1088/2058-6272/ab5866
[4]	P DREWS, H NIEMANN, J COSFELD, Y GAO, J GEIGER, O GRULKE, M HENKEL, D HÖSCHEN, K HOLLFELD, C KILLER, AKRÄMER-FLECKEN, Y LIANG, S LIU, D NICOLAI, O NEUBAUER, M RACK, B SCHWEER, G SATHEESWARAN, L RUDISCHHAUSER, N SANDRI, N WANG, the W-X Team. Magnetic configuration effects on the edge heat flux in the limiter plasma on W7-X measured using the infrared camera and the combined probe[J]. Plasma Science and Technology, 2018, 20(5): 54003-054003. DOI: 10.1088/2058-6272/aaa968
[5]	Pengfei ZHANG (张鹏飞), Ling ZHANG (张凌), Zhenwei WU (吴振伟), Zong XU (许棕), Wei GAO (高伟), Liang WANG (王亮), Qingquan YANG (杨清泉), Jichan XU (许吉禅), Jianbin LIU (刘建斌), Hao QU (屈浩), Yong LIU (刘永), Juan HUANG (黄娟), Chengrui WU (吴成瑞), Yumei HOU (侯玉梅), Zhao JIN (金钊), J D ELDER, Houyang GUO (郭后扬). OEDGE modeling of plasma contamination efficiency of Ar puffing from different divertor locations in EAST[J]. Plasma Science and Technology, 2018, 20(4): 45104-045104. DOI: 10.1088/2058-6272/aaa7e8
[6]	Guozhong DENG (邓国忠), Xiaoju LIU (刘晓菊), Liang WANG (王亮), Shaocheng LIU (刘少承), Jichan XU (许吉禅), Wei FENG (冯威), Jianbin LIU (刘建斌), Huan LIU (刘欢), Xiang GAO (高翔). Modeling of divertor power footprint widths on EAST by SOLPS5.0/B2.5-Eirene[J]. Plasma Science and Technology, 2017, 19(4): 45101-045101. DOI: 10.1088/2058-6272/aa5802
[7]	WANG Dongsheng (王东升), GUO Houyang (郭后扬), SHANG Yizi (尚毅梓), GAN Kaifu (甘开福), WANG Huiqian (汪惠乾), CHEN Yingjie (陈颖杰), et al. Radiative Divertor Plasma Behavior in L- and H-Mode Discharges with Argon Injection in EAST[J]. Plasma Science and Technology, 2013, 15(7): 614-618. DOI: 10.1088/1009-0630/15/7/02
[8]	LI Chengyue (李承跃). Numerical Simulation of the Neutralized α Particle Transport near the Divertor Plate Region[J]. Plasma Science and Technology, 2012, 14(10): 886-890. DOI: 10.1088/1009-0630/14/10/06
[9]	ZHANG Ling, XU Guosheng, DING Siye, GAO Wei, WU Zhenwei, CHEN Yingjie, HUANG Juan. Estimation of Neutral Density in Edge Plasma with Double Null Configuration in EAST[J]. Plasma Science and Technology, 2011, 13(4): 431-434.
[10]	T. TAKIZUKA. Development of the PARASOL Code and Full Particle Simulation of Tokamak Plasma with an Open-Field SOL-Divertor Region Using PARASOL[J]. Plasma Science and Technology, 2011, 13(3): 316-325.

Cited By

Cited by

Periodical cited type(6)

1.	Xie, W., Liang, Y., Jiang, Z. et al. Application of three-dimensional MHD equilibrium calculation coupled with plasma response to island divertor experiments on J-TEXT. Plasma Science and Technology, 2024, 26(11): 115104. DOI:10.1088/2058-6272/ad70e1
2.	Xu, S., Liang, Y., Knieps, A. et al. Modeling of plasma beta effects on the island divertor transport in the standard configuration of W7-X. Nuclear Fusion, 2023, 63(6): 066005. DOI:10.1088/1741-4326/acc7b8
3.	Wang, J., Chen, Z., Cheng, Z. et al. Impurity emissivity tomographic reconstruction by CCD imaging system on J-TEXT. 2023. DOI:10.1109/CIYCEE59789.2023.10401533
4.	Liang, Y., Chen, Z., Wang, N. et al. Towards advanced divertor configurations on the J-TEXT tokamak. Plasma Science and Technology, 2022, 24(12): 124021. DOI:10.1088/2058-6272/acaa8d
5.	Li, B., Wang, T., Nie, L. et al. Reconstruction of the emissivity and flow for Doppler coherence imaging spectroscopy (CIS) on J-TEXT. Fusion Engineering and Design, 2022. DOI:10.1016/j.fusengdes.2022.113271
6.	Li, S., Wang, N., Ding, Y. et al. Impact of the non-axisymmetric SOL current driven by a biased electrode on the diverted J-TEXT plasma. Plasma Physics and Controlled Fusion, 2022, 64(7): 075005. DOI:10.1088/1361-6587/ac72bf

Other cited types(0)

Get Citation

PDF

XML

Article views (198) PDF downloads (299) Cited by(6)

Turn off MathJax

Article Contents

Abstract

References

Influence of the X-point location on edge plasma transport in the J-TEXT tokamak with a high-field-side single-null divertor