Simulation and analysis of the effect of pumping on carbon impurity distribution in HL-2M conventional divertor

doi:10.16568/j.0254-6086.202102001

NUCLEAR FUSION AND PLASMA PHYSICS ›› 2021, Vol. 41 ›› Issue (2): 97-104.DOI: 10.16568/j.0254-6086.202102001

• Plasma Physics • Next Articles

Simulation and analysis of the effect of pumping on carbon impurity distribution in HL-2M conventional divertor

PAN Wei，HUANG Wen-yu, XUE Miao, PENG Yuan-yuan, QU Cheng-hai

(Southwestern Institute of Physics, Chengdu 610041)

Received:2019-12-09 Revised:2020-01-08 Online:2021-06-15 Published:2021-06-24

HL-2M常规偏滤器位形抽气对碳杂质分布影响的模拟分析

周月，郑国尧*，杜海龙，潘宇东，李佳鲜，薛雷，潘卫，黄文玉，薛淼，彭媛媛，曲成海

(核工业西南物理研究院，成都 610041)

作者简介:周月(1992-)，女，黑龙江人，硕士，主要研究聚变装置偏滤器运行模拟计算工作。
基金资助:
国家自然科学基金(11775071，11575056)；国家磁约束核聚变能发展研究专项(2018YFE0301101，2018YFE030- 1104)

Abstract

Abstract: 在小角度V型结构的HL-2M常规偏滤器位形下，采用SOLPS 5.0程序研究了抽气速率S_p对装置粒子排除控制能力及溅射产生的碳杂质分布的影响。模拟结果表明，当进入边缘区域的能量为4MW、上游密度为n_sep=3.0×10¹⁹时，过高的抽气速率(大于40m³•s^-1)将迅速降低靶板附近中性粒子压强和等离子体密度，并引起靶板电子温度T_e的上升和表面材料溅射增强，导致有效电荷量Z_eff升高。在抽气速率约为20~40m³×s^-1时，常规偏滤器的粒子排除效率较高。

Key words: SOLPS 5.0, Standard divertor configuration, Particle control, Heat load, Effective charge Z_eff

摘要： 在小角度V型结构的HL-2M常规偏滤器位形下，采用SOLPS 5.0程序研究了抽气速率S_p对装置粒子排除控制能力及溅射产生的碳杂质分布的影响。模拟结果表明，当进入边缘区域的能量为4MW、上游密度为n_sep=3.0×10¹⁹时，过高的抽气速率(大于40m³•s^-1)将迅速降低靶板附近中性粒子压强和等离子体密度，并引起靶板电子温度T_e的上升和表面材料溅射增强，导致有效电荷量Z_eff升高。在抽气速率约为20~40m³×s^-1时，常规偏滤器的粒子排除效率较高。

关键词: SOLPS 5.0, 偏滤器位形, 粒子控制, 热负载, 有效电荷量Z_eff

CLC Number:

O532+.11

ZHOU Yue, ZHENG Guo-yao, DU Hai-long, PAN Yu-dong, LI Jia-xian, XUE Lei, PAN Wei，HUANG Wen-yu, XUE Miao, PENG Yuan-yuan, QU Cheng-hai. Simulation and analysis of the effect of pumping on carbon impurity distribution in HL-2M conventional divertor[J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2021, 41(2): 97-104.

周月，郑国尧*，杜海龙，潘宇东，李佳鲜，薛雷，潘卫，黄文玉，薛淼，彭媛媛，曲成海. HL-2M常规偏滤器位形抽气对碳杂质分布影响的模拟分析[J]. 核聚变与等离子体物理, 2021, 41(2): 97-104.

References

[1] Jackson G L, Loarte A, Maingi R. A long-pulse high-confinement plasma regime in the Experimental Advanced Superconducting Tokamak [J]. Nature Physics, 2013, 9(12): 817-821.

[2] Divertor I P E G O, Database I P E G O D, Editors I P B. Chapter 4: Power and particle control [J]. Nucl. Fusion, 1999, 39(12): 2391-2469.

[3] Zheng G Y, Xu X Q, Ryutov D D, et al. Magnetic configuration flexibility of snowflake divertor for HL-2M [J]. Fusion Eng. Des., 2014, 89(11): 2621-2627.

[4] Guo H Y, Sang C F, Stangeby P C, et al. Small angle slot divertor concept for long pulse advanced tokamaks [J]. Nucl. Fusion, 2017, 57(4): 044001.

[5] Kawashima H, Shimizu K, Takizuka T, et al. Simulation study for divertor design to handle huge exhaust power in the Slim CS DEMO reactor [J]. Nucl. Fusion, 2009, 49(6): 065007.

[6] Petrie T W, Hill D N, Allen S L, et al. Radiative divertor experiments in DIII-D with D₂ injection [J]. Nucl. Fusion, 1997, 37(3): 321-338.

[7] Pacher H D, Kukushkin A, Coster D, et al. Operating window for high divertor radiation in ITER [J]. J. Nucl. Mater., 1999, 266: 1172-1179.

[8] Divertor I P E G O. Chapter 4: Power and particle control [J]. Nucl. Fusion, 2002, 39(12): 2391-2469.

[9] Leonard A W. Plasma detachment in divertor tokamaks [J]. Plasma Phys. Contr. Fusion, 2018, 60(4): 044001.

[10] Zheng G Y, Xu X Q, Ryutov D D, et al. Magnetic configuration flexibility of snowflake divertor for HL-2M [J]. Fusion Eng. Des., 2014, 89(11): 2621-2627.

[11] Zheng G Y, Cai L Z, Duan X R, et al. Investigations on the heat flux and impurity for the HL-2M divertor [J]. Nucl. Fusion, 2016, 56(12): 126013.

[12] Jin Le, Zhu S Z. Investigation of divertor detachment in EAST by ‘two-point’ model [J]. Plasma Science and Technology, 2007, 9(4): 403-406.

[13] Li J X, Zheng G Y, Song X M, et al. Preliminary study of the X-points control algorithm for advanced divertor configuration on HL-2M [J]. Fusion Eng. Des., 2018, 131: 135-140.

[14] Soukhanovskii V A, Bell R E, Diallo A, et al. Advanced divertor configurations with large flux expansion [J]. J. Nucl. Mater., 2013, 438: S96-S101.

[15] Schneider R, Bonnin X, Borrass K, et al. Plasma edge physics with B2-eirene [J]. Contributions to Plasma Physics, 2006, 46: 3-191.

[16] Chankin A V, Coster D P, Dux R, et al. SOLPS modelling of ASDEX Upgrade H-mode plasma [J]. Plasma Phys. Contr. Fusion, 48(6): 839-868.

Simulation and analysis of the effect of pumping on carbon impurity distribution in HL-2M conventional divertor

HL-2M常规偏滤器位形抽气对碳杂质分布影响的模拟分析

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