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托卡马克高约束H模条件下偏滤器脱靶和热流控制是当前磁约束核聚变研究中的关键物理问题. 脱靶对H模边界输运物理尤其是对芯部约束兼容性的影响是研究偏滤器脱靶物理的关键问题. 本文获得了HL-2A装置H模等离子体偏滤器脱靶与芯部约束兼容的实验结果, 采用OMFIT集成模拟平台, 新发展了偏滤器靶板区的神经网络快速集成模拟方法, 率先采用该快速集成模拟方法开展HL-2A第39007炮高约束模式下, 边界偏滤器脱靶与芯部约束兼容性的集成模拟研究, 经验证集成模拟结果与实验结果相吻合. 通过进一步分析发现: HL-2A装置H模脱靶情况下, 在芯部$ 0.1 < \rho \leqslant {\mathrm{ }}0.5 $的区域内高极向波数($ {k}_{\theta }{\rho }_{{\mathrm{s}}} $>1)模式下的湍性输运以离子温度梯度(ITG)模主导, 在芯部$ 0.5 < \rho \leqslant {\mathrm{ }}0.7 $的区域内的湍性输运以电子湍流主导; 而边界则是在归一化极向波数$ {k}_{\theta }{\rho }_{{\mathrm{s}}} < 2 $的情况下由电子湍流主导, $ {k}_{\theta }{\rho }_{{\mathrm{s}}} > 2 $的情况下则以ITG为主, 并伴有少量的电子湍流. 本文研究结果为托卡马克装置芯边耦合物理研究提供了一定的集成模拟与实验验证基础.The divertor detachment and heat flux control under high-confinement H-mode conditions in tokamaks represent critical physical challenges in current magnetic confinement fusion research. Understanding the influence of detachment on H-mode boundary transport physics, particularly its compatibility with core confinement, is central to resolving divertor detachment physics. In this study, experimental results on divertor detachment and core confinement compatibility in H-mode plasma from the HL-2A tokamak are presented. On the objective MHD framework for integrated tasks (OMFIT) integrated modeling platform, a novel neural network-based fast integrated modeling method for the divertor target region is developed by integrating a new edge neural network module (Kun-Lun Neural Networks, KLNN) to enhance divertor, scrape-off-layer and edge pedestal fast prediction capability. For the first time, this method is used to conduct integrated simulations of divertor detachment and core confinement compatibility in HL-2A discharge #39007 under high-confinement mode. The simulation results are validated with experimental measurements, demonstrating that they are well consistent. Further analysis reveals that in HL-2A H-mode detachment scenarios, turbulent transport in the core region ($ 0.1 < \rho \leqslant 0.5 $) with high poloidal wave numbers $ ({k}_{\theta }{\rho }_{{\mathrm{s}}} > 1 $) is dominated by ion temperature gradient (ITG) mode, while electron-driven turbulence prevails in the region $ (0.5 < \rho \leqslant 0.7) $. In the boundary region, electron turbulence dominates at low normalized poloidal wave numbers ($ {k}_{\theta }{\rho }_{{\mathrm{s}}} < 2 $), whereas ITG modes become predominant at higher wave numbers ($ {k}_{\theta }{\rho }_{{\mathrm{s}}} > 2 $), accompanied by minor electron turbulence contributions. The research results of this work provide a certain foundation for integrated simulation and experimental verification in the study of core-edge coupling physics in tokamak devices and some insights for understanding detachment-compatible H-mode scenarios in the next-step fusion devices.
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Keywords:
- tokamak /
- detachment /
- H mode /
- integrated simulation
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图 1 包含KLNN程序的OMFIT等离子体剖面集成模拟工作流
Fig. 1. Integrated simulation workflow of OMFIT plasma profiles incorporating KLNN program.
图 4 HL-2A装置第39007炮等离子体放电参数随时间演化图 (a)等离子体储能; (b)等离子体电流; (c)电子线平均密度; (d)归一化比压$ {\beta }_{{\mathrm{n}}} $; (e) NBI, ECRH和 LHCD辅助加热功率; (f) $ {D}_{{\mathrm{\alpha }}} $射线
Fig. 4. Time evolution of the dischargement parameters of the shot #39007 in HL-2A: (a) Plasma stored energy; (b) plasma current; (c) average electron line density; (d) $ {\beta }_{{\mathrm{n}}} $; $ \left({\mathrm{e}}\right) $ auxiliary heating power $ {P}_{{\mathrm{N}}{\mathrm{B}}{\mathrm{I}}} $, $ {P}_{{\mathrm{E}}{\mathrm{C}}{\mathrm{R}}{\mathrm{H}}} $ and $ {P}_{{\mathrm{L}}{\mathrm{H}}{\mathrm{C}}{\mathrm{D}}} $; (f) $ {D}_{{\mathrm{\alpha }}} $ray.
图 5 (a)真空室区等离子体辐射强度随时间演化图; (b)偏滤器靶板区等离子体辐射强度随时间演化图
Fig. 5. (a) Time evolution of plasma radiation intensity in the vacuum chamber area; (b) time evolution of plasma radiation intensity in the divertor target plate area.
图 6 等离子体边界靶板探针测得的热流通量随时间演化图
Fig. 6. Time evolution of heat flux measured by the plasma boundary target plate probe.
图 7 等离子体边界靶板探针测得的离子饱和流强度随时间演化图
Fig. 7. Time evolution of ion saturated current intensity measured by the plasma boundary target plate probe.
图 8 第39007炮在1320 ms时的实验值与输入剖面 (a)电子密度剖面; (b)电子温度剖面
Fig. 8. Experiment and input profiles of the shot #39007 at the 1320 ms: (a) Electron density; (b) electron temperature.
图 9 第39007炮在1320 ms时刻的实验值与集成模拟初始输入剖面 (a)离子温度$ {T}_{{\mathrm{i}}} $; (b)旋转速度$ \omega $
Fig. 9. Experimental values and the initial input profiles of the integrated simulation of the shot #39007 at the 1320 ms: (a) Ion temperature $ {T}_{{\mathrm{i}}} $; (b) rotation $ \omega $.
图 10 OMFIT集成平台TGYRO程序中不同物理量第0次和第10次迭代结果对比 (a)离子温度$ {T}_{{\mathrm{i}}} $; (b)电子温度$ {T}_{{\mathrm{e}}} $; (c)旋转速度$ \omega $
Fig. 10. Comparison of the results of the 0 th and 10 th iterations of different physical quantities in the TGYRO program of the OMFIT integrated platform: (a) Ion temperature $ {T}_{{\mathrm{i}}} $; (b) electron temperature $ {T}_{{\mathrm{e}}} $; (c) rotation $ \omega $.
图 11 OMFIT集成平台TGYRO程序中各物理量不同径向位置最后10次迭代演化结果 (a)离子温度$ {T}_{{\mathrm{i}}} $; (b)电子温度$ {T}_{{\mathrm{e}}} $; (c)旋转速度$ \omega $.
Fig. 11. Evolution results of the last 10 iterations of various physical quantities at different radial positions in the TGYRO program of the OMFIT integrated platform: (a) Ion temperature $ {T}_{{\mathrm{i}}} $; (b) electron temperature $ {T}_{{\mathrm{e}}} $; (c) rotation $ \omega . $
图 12 第39007炮在1320 ms时刻各物理量剖面的模拟结果与实验结果对照 (a)电子密度$ {n}_{{\mathrm{e}}} $; (b)电子温度$ {T}_{{\mathrm{e}}} $; (c)离子温度$ {T}_{{\mathrm{i}}} $; (d)旋转速度$ \omega $
Fig. 12. Comparison between the simulation results and experimental results of the physical quantity profiles of the shot #39007 at the 1320 ms: (a) Electron density $ {n}_{{\mathrm{e}}} $; (b) electron temperature $ {T}_{{\mathrm{e}}} $; (c) ion temperature $ {T}_{{\mathrm{i}}} $;$(d) rotation $ \omega . $
图 13 第39007炮1320 ms时刻压强剖面的实验与模拟对照
Fig. 13. Comparison of experiment and simulation pressure profiles of the shot # 39007 at the 1320 ms.
图 14 第 39007 炮在1320 ms时刻的各成分电流剖面
Fig. 14. Current profiles of each composition of the shot #39007 at the 1320 ms.
图 15 第39007炮1320 ms时刻NBI注入的能量密度沉积分布
Fig. 15. Energy density deposition distribution of NBI of the shot # 39007 at the 1320 ms.
图 16 第39007炮放电在1320 ms时刻模拟后得到的 (a)离子能量通量和(b)电子能量通量
Fig. 16. Ion energy flux (a) and electron energy flux (b) of the shot #39007 at the 1320 ms after simulation.
图 17 HL-2A装置第39007炮在1320 ms, $ \rho =0.1—0.99 $区域内最不稳定的两支本征模式的频谱
Fig. 17. Frequency spectrum of the two most unstable eigenmodes in the $ \rho =0.1-0.99 $ region of the shot #39007 at the 1320 ms in HL-2A.
图 18 39007炮在1320 ms, $ \rho =0.3, 0.6, 0.9, 0.95 $处线性不稳定性的增长率与波数的关系(蓝色为离子抗磁漂移方向, 红色为电子抗磁漂移方向)
Fig. 18. Relationship between the growth rate of linear instability and the wave number in the $ \rho =0.3, {\mathrm{ }}{\mathrm{ }}{\mathrm{ }}{\mathrm{ }}0.6, {\mathrm{ }}0.9, {\mathrm{ }}0.95 $ of the shot #39007 at the 1320 ms (The blue color indicates the direction of the ion diamagnetic drift, the red color indicates the direction of the electron diamagnetic drift).
表 1 HL-2A #39007炮1320 ms时刻等离子体参数的实验值与模拟初始输入值对比表
Table 1. Comparison table of experimental values and initial input values of simulation for plasma parameters of the shot #39007 at the 1320 ms in HL-2A.
物理量 实验值 模拟初始输入值 等离子体电流/kA 150 150 纵场强度/T 1.33 1.33 NBI功率/kW 600 600 ECRH功率/kW 850 850 LHCD功率/kW 450 450 欧姆电流占比 — 0.60 NBI驱动电流占比 — 0.13 自举电流占比 — 0.27 芯部离子温度/keV 0.51 0.52 芯部电子温度/keV 2.25 2.26 芯部电子密度/(1019 m–3) 2.62 2.52 电子线平均密度/(1019 m–3) 1.83 1.91 Greenwald密度极限比值 0.42 0.43 q95 3.32 3.07 归一化比压 1.67 1.75 
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表 2 HL-2A #39007炮脱靶前后时段平均的储能、能量约束时间以及$ {H}_{98} $因子变化对比表
Table 2. The comparison table of Changes in average stored energy, average energy confinement time and average $ {H}_{98} $ factor during the time periods before and after detachment of the shot #39007 in HL-2A.
储能/kJ 能量约束时间/ms $ {H}_{98} $因子 脱靶前时间段
(1100—1180 ms)29.2 ± 1.699 19.86 ±1.24 1.06 ± 0.069 脱靶后时间段
(1300—1380 ms)27.8 ± 1.883 18.96 ± 1.25 1.02 ± 0.066 下降百分比/% 4.8 4.5 3.8
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