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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 magnetohydrodynamic 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 $), accompanied by minor electron turbulence contributions. The research results of this work provide a certain foundation for integrated simulation and experimental verification in the study of core-edge coupling physics in tokamak devices and some insights for understanding detachment-compatible H-mode scenarios in the next-step fusion devices.
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Keywords:
- tokamak /
- detachment /
- H mode /
- integrated simulation
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图 1 包含KLNN程序的OMFIT等离子体剖面集成模拟工作流
Figure 1. Integrated simulation workflow of OMFIT plasma profiles incorporating KLNN program.
图 2 KLBJ-NN 程序的神经网络结构
Figure 2. Neural network structure of KLBJ-NN program.
图 3 KLTJ-NN 程序的神经网络结构
Figure 3. Neural network structure of KLTJ-NN program.
图 4 HL-2A装置第39007炮等离子体放电参数随时间演化图 (a)等离子体储能; (b)等离子体电流; (c)电子线平均密度; (d)归一化比压$ {\beta }_{{\mathrm{n}}} $; (e) NBI, ECRH和 LHCD辅助加热功率; (f) $ {D}_{{\mathrm{\alpha }}} $射线
Figure 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}}} $; (e) 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 }}} $ray.
图 5 (a)真空室区等离子体辐射强度随时间演化图; (b)偏滤器靶板区等离子体辐射强度随时间演化图
Figure 5. (a) Time evolution of plasma radiation intensity in the vacuum chamber area; (b) time evolution of plasma radiation intensity in the divertor target plate area.
图 6 等离子体边界靶板探针测得的热流通量随时间演化图
Figure 6. Time evolution of heat flux measured by the plasma boundary target plate probe.
图 7 等离子体边界靶板探针测得的离子饱和流强度随时间演化图
Figure 7. Time evolution of ion saturated current intensity measured by the plasma boundary target plate probe.
图 8 第39007炮在1320 ms时的实验值与输入剖面 (a)电子密度剖面; (b)电子温度剖面
Figure 8. Experiment and input profiles of the shot #39007 at the 1320 ms: (a) Electron density; (b) electron temperature.
图 9 第39007炮在1320 ms时刻的实验值与集成模拟初始输入剖面 (a)离子温度$ {T}_{{\mathrm{i}}} $; (b)旋转速度$ \omega $
Figure 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 $
Figure 10. Comparison of the results of the 0th and 10th 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 $.
Figure 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 $
Figure 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
Figure 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
Figure 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
Figure 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
Figure 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
Figure 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)
Figure 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H98因子变化对比表
Table 2. Comparison table of changes in average stored energy, average energy confinement time and average H98 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
DownLoad: CSV
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[1] 孙有文, 仇志勇, 万宝年 2024 73 175202
Google Scholar
Sun Y W, Qiu Z Y, Wan B N 2024 Acta Phys. Sin. 73 175202
Google Scholar
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Google Scholar
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Google Scholar
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Google Scholar
[5] 孟令义 2022 博士学位论文 (合肥: 中国科学技术大学)
Meng L Y 2022 Ph. D. Dissertation (Hefei: University of Science and Technology of China
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Google Scholar
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Google Scholar
Qin C C, Mou M L, Chen S Y 2023 Acta Phys. Sin. 72 045203
Google Scholar
[8] 龙婷, 柯锐, 吴婷, 高金明, 才来中, 王占辉, 许敏 2024 73 088901
Google Scholar
Long T, Ke R, Wu T, Gao J M, Cai L Z, Wang Z H, Xu M 2024 Acta Phys. Sin. 73 088901
Google Scholar
[9] Luce T C, Challis C D, Ide S, Joffrin E, Kamada Y, Politzer P A, Schweinzer J, Sips A C C, Stober J, Giruzzi G, Kessel C E, Murakami M, Na Y S, Park J M, Polevoi A R, Budny R V, Citrin J, Garcia J, Hayashi N, Hobirk J, Hudson B F, Imbeaux F, Isayama A, McDonald D C, Nakano T, Oyama N, Parail V V, Petrie T W, Petty C C, Suzuki T, Wade M R, the ITPA Integrated Operation Scenario Topical Group Members, the ASDEX-Upgrade Team, the DIII-D Team, JET EFDA Contributors, the JT-60U Team 2014 Nucl. Fusion 54 013015
Google Scholar
[10] Imbeaux F, Pinches S D, Lister J B, Buravand Y, Casper T, Duval B, Guillerminet B, Hosokawa M, Houlberg W, Huynh P, Kim S H, Manduchi G, Owsiak M, Palak B, Plociennik M, Rouault G, Sauter O, Strand P 2015 Nucl. Fusion 55 123006
Google Scholar
[11] Meneghini O, Smith S P, Lao L L, Izacard O, Ren Q, Park J M, Candy J, Wang Z, Luna C J, Izzo V A, Grierson B A, Snyder P B, Holland C, Penna J, Lu G, Raum P, McCubbin A, Orlov D M, Belli E A, Ferraro N M, Prater R, Osborne T H, Turnbull A D, Staebler G M, the ATOM Team 2015 Nucl. Fusion 55 083008
Google Scholar
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Google Scholar
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Google Scholar
Luo Y M, Wang Z H, Chen J L, Wu X K, Fu C L, He X X, Liu L, Yang Z C, Li Y G, Gao J M, Du H R, Kunlun Integrated Simulation and Design Group 2022 Acta Phys. Sin. 71 075201
Google Scholar
[14] 罗一鸣 2022 硕士学位论文 (成都: 核工业西南物理研究院)
Luo Y M, 2022 M S Thesis (Chendu: Southwestern Institute of Physics
[15] John H S, Taylor T S, Lin-Liu Y R, Turnbull A D 1994 Plasma Phys. Controlled Fusion 3 603
Google Scholar
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Google Scholar
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Google Scholar
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Google Scholar
[19] Yang C, Bonoli P T, Wright J C, Ding B J, Parker R, Shiraiwa S, Li M H 2014 Plasma Phys. Control. Fusion 56 125003
Google Scholar
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Google Scholar
Fan H, Chen S Y, Mou M L, Liu T Q, Zhang Y M, Tang C J 2024 Acta Phys. Sin. 73 095204
Google Scholar
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Google Scholar
[23] Moscheni M, Wigram M, Wu H, Meineri C, Carati C, De Marchi E, Greenwald M, Innocente P, LaBombard B, Subba F, Zanino R 2025 Nucl. Fusion 65 026025
Google Scholar
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