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近期, 在中国环流器2号A (HL-2A)装置上利用电子回旋共振加热(electron cyclotron resonance heating, ECRH)开展了鱼骨模主动控制的实验研究. 结果发现, 鱼骨模的主动控制效果与射频波功率沉积位置密切相关. 在相同的注入功率条件下, ECRH离轴加热的效果比在轴的效果更好, 甚至可以实现对鱼骨模的完全抑制. 分析表明, 大功率离轴射频波通过提升电子温度进而使得等离子体压强梯度和等离子体电流密度变化, 随后导致安全因子改变并使得最小安全因子
$q_{{\rm{min}}}>1$ . M3D-K程序模拟表明, 鱼骨模的增长率随着$q_{{\rm{min}}}$ 增大而减小, 这意味着ECRH通过提高安全因子导致q = 1有理面的缺失并使得鱼骨模被完全抑制.Experiment on suppressing fishbone activities is carried out in HL-2A tokamak by electron cyclotron resonance heating (ECRH). To achieve multiple deposition locations of ECRH, the magnetic field is in a range of 1.22–1.4 T from shot to shot. It is found that the fishbone modes exhibit different characteristics at different radial deposition locations. With the same injected power, the effect of off-axis ECRH is much better than that of on-axis heating. The fishbone modes can be completely suppressed when ECRH is deposited nearby the q = 1 rational surface, but would only mitigate in other cases. Further analysis indicate that injection of high power ECRH leads the electron temperature to increase, then the pressure gradient and plasma current density to change, finally safety factor to change and the minimum safety factor to reach a value larger than 1. Meanwhile, M3D-K simulation results show that the growth rate of fishbone mode declines with the increase of qmin. In other words, the growth of safety factor and disappearance of q = 1 rational surface induced by ECRH contribute to the suppression of fishbone activities. The experimental results reported here may not only help to better understand complex effects of ECRH on magnetohydrodynamic instability, but also provide a physics basis for actively controlling the energetic particle driven modes in the future magnetic confined fusion devices.-
Keywords:
- electron cyclotron resonance heating /
- deposition location /
- active control /
- fishbone modes
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图 1 HL-2A 装置第27214次(黑)和第27216次(红)放电的实验参数 (a)等离子体电流; (b)环向磁场; (c)电子线平均密度(实线)及反馈送气电压信号(点线); (d)电子温度; (e)离子温度; (f)旋转频率; (g)等离子体比压; (h)中性束注入功率(实线)和电子回旋共振加热功率(虚线)
Fig. 1. History evolution of basic parameters during the 27214 and 27216 discharges on HL-2A tokamak: (a) Plasma current; (b) toroidal magnetic field; (c) line-averaged electron density (solid) and voltage signal of gas puffing (dot); (d) electron temperature; (e) ion temperature; (f) rotation frequency; (g) plasma beta; (h) power of NBI and ECRH
图 2 第27214次(黑)和27216次(红)放电过程中ECRH功率沉积分布
Fig. 2. Power deposition position of ECRH during the 27214 (black) and 27216 (red) discharges.
图 3 第27214次(a)和27216次(b)放电的磁探针频谱, 其中黑色线为ECRH注入功率 (×40)
Fig. 3. Magnetic spectrum for the 27214 (a) and 27216 (b) discharges. Noted that, the black curves are the power of ECRH (
$ \times 40 $ ).
图 4 第27216次等离子体放电过程中反剪切阿尔芬本征模频率和最小安全因子
Fig. 4. Temporal frequency of reversed shear Alfvén eigenmode and minimum safety factor during the 27216 discharge.
图 5 第27214次(黑)和27216次(红)放电750 ms 时刻的平衡参数剖面 (a)电子密度
$ n_{\rm{e}} $ ; (b)旋转频率$ f_{{\rm{rot}}} $ ; (c)电子温度$ T_{\rm{e}} $ , 虚线为电子温度内部输运垒的根部位置; (d)离子温度$ T_{\rm{i}} $ ; (e)等离子体压强$ P=n_{\rm{e}}(T_{\rm{e}}+T_{\rm{i}})K $ , K为开尔文常数; (f)安全因子Fig. 5. Basic profiles at 750 ms for the 27124 (black) and 27216 (red) discharges: (a) Electron density
$ n_{\rm{e}} $ ; (b) plasma rotation frequency$ f_{{\rm{rot}}} $ ; (c) electron temperature$ T_{\rm{e}} $ , the dotted lines indicate locations of internal transport barrier in electron temperature; (d) ion temperature$ T_{\rm{i}} $ ; (e) plasma pressure$ P=n_{\rm{e}}(T_{\rm{e}}+T_{\rm{i}})K $ , K is the Kelvin constant; (f) safety factor
图 6 第27214 (a)和27216 (b)次放电过程中750 ms 时刻归一化压强梯度(
$ R/L_{\rm{P}} $ , 红)、电子温度梯度($ R/L_{T_{\rm{e}}} $ , 黑)、离子温度梯度(R/$ L_{T_{\rm{i}}} $ , 蓝)和电子密度梯度($ R/L_{n_{\rm{e}}} $ , 绿)的特征长度Fig. 6. Normalized scale length of pressure gradient (
$ R/L_{\rm{P}} $ , red), electron temperature gradient ($ R/L_{T_{\rm{e}}} $ , black), ion temperature gradient ($ R/L_{T_{\rm{i}}} $ , blue), electron density gradient ($ R/L_{n_{\rm{e}}} $ , green) at 750 ms for the 27214 (a) and 27216 (b) discharges.
图 7 第27214次(左)和27216次(右)放电700—750 ms 之间的(a1), (a2)电子温度分布、(b1), (b2)电子温度梯度、(c1), (c2)等离子体压强梯度
Fig. 7. (a1), (a2) Electron temperature profile, (b1), (b2) temperature gradient and (c1), (c2) pressure gradient during 700–750 ms for the 27124 (left) and 27216 (right) discharges.
图 8 (a)具有不同最小值的安全因子分布, 其中蓝色曲线为第27214次放电750 ms时刻的安全因子分布, 上下方两曲线的偏移量分别为
$ \Delta q=0.09 $ ,$ \Delta q=0.06 $ ,$ \Delta q=-0.02 $ ,$ \Delta q=-0.05 $ ; (b)鱼骨模增长率与最小安全因子的关系Fig. 8. (a) Safety factor profiles with different minimum safety factors, the blue one is the safety factor profile at 750 ms for the 27214 discharge, the two upper and below curves are the safety factors with a offset of
$ \Delta q=0.09 $ ,$ \Delta q=0.06 $ ,$ \Delta q=-0.02 $ ,$ \Delta q=-0.05 $ ; (b) relationship between the growth rate of fishbone mode and minimum safety factors. -
[1] McGuire K, Goldston R, Bell M, et al. 1983 Phys. Rev. Lett. 50 891
Google Scholar
[2] Chen L, White R B, Rosenbluth M N 1984 Phys. Rev. Lett. 52 1122
Google Scholar
[3] Heidbrink W W, Sager G 1990 Nucl. Fusion 30 1015
Google Scholar
[4] Nave M F F, Campbell D J, Joffrin E, et al. 1991 Nucl. Fusion 31 697
Google Scholar
[5] Zonca F, Chen L, Botrugno A, et al. 2009 Nucl. Fusion 49 085009
Google Scholar
[6] Wong K L, Chu M S, Luce T C, et al. 2000 Phys. Rev. Lett. 85 996
Google Scholar
[7] Yu L M, Ding X T, Chen W, et al. 2013 Nucl. Fusion 53 053002
Google Scholar
[8] Perez von Thun C, Perona A, Johnson T, et al. 2010 Nucl. Fusion 50 084009
Google Scholar
[9] Perez von Thun C, Salmi A, Perona A, et al. 2012 Nucl. Fusion 52 094010
Google Scholar
[10] Kiptily V G, Fitzgerald M, Goloborodko V, et al. 2018 Nucl. Fusion 58 014003
Google Scholar
[11] Anderson D, Elevant T, Hamnén H, et al. 1993 Fusion Sci. Tech. 23 5
Google Scholar
[12] Hender T C, Buratti P, Casson F J, et al. 2016 Nucl. Fusion 56 066002
Google Scholar
[13] Fredrickson E D, Belova E V, Battaglia D J, et al. 2017 Phys. Rev. Lett. 118 265001
Google Scholar
[14] Bortolon A, Heidbrink W W, Kramer G J, et al. 2013 Phys. Rev. Lett. 110 265008
Google Scholar
[15] Maslovsky D, Levitt B, Mauel M E, et al. 2003 Phys. Rev. Lett. 90 185001
Google Scholar
[16] Nagaoka K, Ido T, Ascasíbar E, et al. 2013 Nucl. Fusion 53 072004
Google Scholar
[17] Van Zeeland M A, Heidbrink W W, Nazikian R, et al. 2009 Nucl. Fusion 49 065003
Google Scholar
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Google Scholar
[19] Yamamoto S, Nagasaki K, Kobayashi S, et al. 2017 Nucl. Fusion 57 126065
Google Scholar
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Google Scholar
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Google Scholar
[22] Seol J, Lee S G, Park B H, et al. 2012 Phys. Rev. Lett. 109 195003
Google Scholar
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Google Scholar
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Google Scholar
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Google Scholar
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Google Scholar
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Google Scholar
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Google Scholar
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Google Scholar
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Google Scholar
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Google Scholar
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Google Scholar
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Google Scholar
[34] Chen W, Wang Z X 2020 Chin. Phys. Lett. 37 125001
Google Scholar
[35] Heidbrink W W 2002 Phys. Plasmas 9 2113
Google Scholar
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