Integrated simulation of plasma current profile in HL-2A high confinement mode(H mode)

Zhang Hong-Ming; Wu Jing; Li Jia-Xian; Yao Lie-Ming; Xu Jiang-Cheng; Wu Yan-Zhan; Liu Qi-Yan; Guo Peng-Cheng

doi:10.7498/aps.70.20210945

Abstract

The plasma current (I_p), magnetic field (B), and safety factor distribution (q profile) of the HL-2A tokamak device are crucial to monitoring the steady-state operational scenarios (in high confinement mode, H mode). Based on real experimental data and integrated modeling simulation method (OMFIT), the plasma parameters’ profiles such as magnetic field configuration and current density profiles in H mode were reconstructed. By building up an integrated simulation platform for dynamic equilibrium configuration, and combining the rapid workflow processing method and experimental data with integrated simulation models, the ion and electron temperature, density, and current density profiles were obtained. The integration simulation platform was established to reconstruct the internal magnetic surface configuration, the plasma boundary parameter distribution, the ion/electron temperature, current density, and the q profile. The Ohmic current, bootstrap current, and radio-frequency current profiles with its fractions were calculated. The width of the pedestal region was about 7.52 cm according to our simulation results. It was found that the pressure gradient changes its direction at radial coordinate ρ(r/a) = 0.1 and reaches its maximum value near ρ = 0.7, which may be the internal transport barrier (ITB) configuration caused by negative shear. The profile reconstruction and real-time monitoring of the physical parameters are conducive to evaluating the quality of H mode discharge experiment and can assist in the steady-state operation of advanced operating modes such as HL-2M high normalized beta (β_n) discharge.

Keywords:

Authors and contacts

1.
School of Physics, University of Electronic Science and Technology of China, Chengdu 611731, China
2.
Fusion Research Institute, Southwestern Institute of Physics, Chengdu 610225, China

Corresponding author: Wu Jing, wujing@uestc.edu.cn ; Li Jia-Xian, lijx@swip.ac.cn ; Yao Lie-Ming, ylm@uestc.edu.cn ;

Funds: Project supported by the National Key Research and Development Program of China (Grant No. 2019YFE03020004).

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References

[1]	Wagner F 1982 Phys. Re. Lett. 49 1408 Google Scholar
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Cited By

图 1 HL-2A高约束模式(H模)放电模拟循环示意图

Figure 1. Design and analysis of HL-2A high confinement model (H model) discharge integrated simulation workflow.

DownLoad: Full-Size Img PowerPoint

图 2 HL-2A炮号#37012放电参数

Figure 2. Shot #37012 parameters of HL-2A discharge.

DownLoad: Full-Size Img PowerPoint

图 3 HL-2A托卡马克平衡物理参数实验数据　(a)等离子体中离子温度T_i径向分布; (b)电子温度T_e径向分布; (c)电子密度n_e径向分布

Figure 3. (a) Radial distribution profile of ion temperature T_i in HL-2A Tokamak plasma; (b) radial distribution profile of electron temperature T_e in HL-2A Tokamak plasma; (c) radial distribution profile of electron density n_e in HL-2A tokamak plasma.

DownLoad: Full-Size Img PowerPoint

图 4 HL-2A 实验数据处理，物理参数拟合径向分布和OMFIT耦合流程

Figure 4. Flow chart for getting fitting curve processing by using discrete and interpolation of HL-2A experimental data

DownLoad: Full-Size Img PowerPoint

图 5 采用集成模拟程序OMFIT重建的 (a) HL-2A的电子温度T_e和离子温度T_i剖面; (b)电子密度n_e剖面

Figure 5. Reconstruction of HL-2A parameters by OMFIT integrated simulation code: (a) Electron temperature T_e and ion temperature T_i profiles; (b) electron density n_e profile.

DownLoad: Full-Size Img PowerPoint

图 6 HL-2A托卡马克等离子体电子密度(a)、电子温度(b)、离子温度(c)和旋转角速度(d)随径向剖面的集成模拟和实验拟合结果对比

Figure 6. HL-2A Tokamak electron density (a), electron temperature(b), ion temperature (c), rotational angular velocity, and (d) versus radial profile by OMFIT and experimental fitting in shot #37012.

DownLoad: Full-Size Img PowerPoint

图 7 集成模拟程序OMFIT得到的HL-2A托卡马克等离子体磁场位形结构图 (a); 等离子体压强（单位Pa）径向剖面分布(b); 压强梯度P’（无量纲）径向分布(c); 安全因子q（无量纲）随着径向变化分布剖面(d); 极向电流梯度FF'（A/m³）径向分布剖面(e)

Figure 7. HL-2A Tokamak plasma magnetic field configuration obtained by integrated simulation code OMFIT (a); pressure profile(unit Pa) (b); profile distribution of the pressure gradient(Dimensionless quantity) (c); profile distribution of safety factor q (Dimensionless quantity) obtained (d); profile distribution of the polar current gradient FF' (unit A/m³)(e).

DownLoad: Full-Size Img PowerPoint

图 8 (a)磁约束托卡马克装置shot #37012由集成模拟程序OMFIT计算的整体电流密度、包含中性束电流密度、自举电流密度、欧姆电流密度和射频电流密度及份额分布曲线; (b)OMFIT程序和平衡反演程序EFIT计算的安全因子q剖面对比图

Figure 8. (a) Magnetic confinement Tokamak device shot #37012 total current densities calculated by the integrated simulation program OMFIT, including neutral beam current density, bootstrap current density, Ohmic current density, and RF current density with percentages of respective current densities in total current densities; (b) comparison of the safety factor q profiles calculated by the OMFIT program and the balance inversion code EFIT.

DownLoad: Full-Size Img PowerPoint

[1]	Wagner F 1982 Phys. Re. Lett. 49 1408 Google Scholar
[2]	李凯 2020 博士学位论文 (合肥: 中国科学技术大学) Li K 2020 Ph. D. Dissertation (Hefei: University of Science and Technology of China) (in Chinese)
[3]	钟武律, 段旭如 2020 原子核物理评论 37 462 Google Scholar Zhong W L, Duan X R 2020 Nucl. Phys. Re. 37 462 Google Scholar
[4]	Snyder P B, Aiba N, Beurskens M 2009 Nucl. Fusion 49 085035 Google Scholar
[5]	Stacey W M, Groebner R J 2003 Phys. Plasm. 10 2412 Google Scholar
[6]	Lao L L, Ferron J R, Groebner R J, et al. 1990 Nucl. Fusion 30 103549
[7]	Fellinger P, Marklein R, Langenberg K J, Klaholz S 1995 Wave Motion 21 47 Google Scholar
[8]	陈文锦, 何小雪, 刘亮, 魏彦玲, 马倩, 余德良 2016 核聚变与等离子体物理 36 104 Google Scholar Chen W J, He X X, Liu L, Wei Y L, Ma Q, Yu D L 2016 Nucl. Fusion Plasma Phys. 36 104 Google Scholar
[9]	Logan N C, Grierson, B A, Haskey S R, Smith S P, Meneghini O, Eldon D 2018 Nucl. Fusion 74 125 Google Scholar
[10]	Meneghini O, Lao L 2013 Plasma Fusion Res. 8 2403009 Google Scholar
[11]	Meneghini O, Smith S P, Lao L L, Izacard O, et al. 2015 Nucl. Fusion 55 083008 Google Scholar
[12]	吴木泉 2020 博士学位论文 (合肥: 中国科学技术大学) Wu M Q 2020 Ph. D. Dissertation (Hefei: University of Science and Technology of China) (in Chinese)
[13]	李强 2009 原子能科学技术 S2 204 Li Q 2009 Atomic Energy Sci. Technol. S2 204 (in Chinese)
[14]	饶军, 陆志鸿, 张劲松等 2009 核聚变与等离子体物理 29 324 Google Scholar Rao J, Lu Z H, Zhang J S, et al. 2009 Nucl. Fusion Plasma Phys. 29 324 Google Scholar
[15]	Owen L W, Canik J M, Groebner R J, et al. 2010 Nucl. Fusion 50 64017 Google Scholar
[16]	Beurskens M N A, Giudicotti L, Kempenaarsl M, et al. 2008 Re. Scient. Instrum. 79 10.1063
[17]	Candy J, Holland C, Waltz R E, et al. 2009 Phys. Plasmas 16 2137
[18]	Staebler G M, Belli E A, Candy J, Kinsey J E, Dudding H, Patel B 2021 Nuclear Fusion 61 116007 Google Scholar
[19]	Staebler G M, Kinsey J E, Belli E A, et al. 2014 Phys. Plasmas 21 1596
[20]	Belli E A, Candy J, Angioni C 2014 Plasma Phys. Control. Fusion 56 124002 Google Scholar
[21]	Shaing K C, Lai A L 2013 Phys. Plasmas 20 122504 Google Scholar
[22]	Hubbard A E, Boivin R L, Granetz R S, et al. 1998 Phys. Plasmas 5 1744 Google Scholar
[23]	Belli E A, Candy J 2021 Phys. Plasmas 28 062301 Google Scholar
[24]	Staebler G M, Candy J, Belli E A, Kinsey J E, Bonanomi N, Patel B 2021 Plasma Phys. Control. Fusion 63 015013 Google Scholar
[25]	Snyder P B, Groebner R J, Hughes J W, et al. 2011 Nucl. Fusion 51 103016 Google Scholar
[26]	Gao X, Zhang T, Han X, et al. 2015 Nucl. Fusion 55 083015 Google Scholar
[27]	Groebner R J, Baker D R, Burrell K H, et al. 2001 Nucl. Fusion 41 1789 Google Scholar
[28]	Groebner R J, Osborne T H 1998 Phys. Plasmas 5 1800 Google Scholar
[29]	Kinsey J E, Staebler G M, Candy J, et al. 2011 Nucl. Fusion 51 83001 Google Scholar
[30]	McDonald D C, Cordey J G, Thomsen K, 2007 Nucl. Fusion 47 147 Google Scholar
[31]	Saibene G, Sartori R, Loarte A, et al. 2002 Plasma Phys. Control. Fusion 44 1769 Google Scholar

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