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锯齿振荡是托卡马克装置上常见的磁流体不稳定性之一. 先进实验超导托卡马克(experimental advanced superconducting Tokamak, EAST)装置放电中观察到外加共振磁扰动(resonant magnetic perturbation, RMP)会影响锯齿振荡行为. 本文研究了环向模数n = 2的RMP对锯齿周期的影响. 通过RMP线圈相位差扫描实验发现, 当RMP上下线圈(n = 2)相位差
$ \Delta {\phi }_{{\rm{U}}{\rm{L}}} $ 发生变化时, 扰动场的谱型发生变化, 锯齿周期和崩塌幅度也随之发生明显的改变. 单流体电阻磁流体力学 (MARS-F)程序分析表明, 在相同实验条件下, 当RMP上下线圈(n = 2)相位差为$\Delta {\phi }_{{\rm{U}}{\rm{L}}}=270^\circ$ 时, 等离子体芯部区域的响应最强, 此时锯齿周期和幅度最小. 锯齿行为的改变可能与RMP引起的快离子损失相关. 该研究利用RMP上下线圈(n = 2)实现对锯齿行为的有效调控, 有利于未来EAST发展高比压放电条件下的大锯齿自动控制技术.-
关键词:
- 先进实验超导托卡马克 /
- 共振磁扰动 /
- 锯齿振荡
Sawtooth oscillation is one of the most important magneto-hydrodynamic (MHD) instabilities in Tokamak plasma, which can result in the periodic relaxation of the temperature and density of the core plasma when the safety factor on the magnetic axis (q0) is lower than unity. Owing to the periodic relaxation of the plasma core parameters, sawtooth oscillations are beneficial to avoiding impurity accumulation in plasma core. However, the large sawtooth crash may trigger off other MHD instabilities, like tearing modes (TMs) or neoclassical tearing modes (NTMs), which is a matter of concern for the plasma stability. Therefore, it is essential to control sawtooth oscillations for ensuring safe operation in the future Tokamaks such as ITER. The resonant magnetic perturbation (RMP) is widely used to control edge-localized modes (ELMs) and divertor heat flux in Tokamak. The application of RMP has also been found to affect the sawtooth behaviors. This paper studies the influence of RMP coils at n = 2 on sawtooth behaviors in experimental advanced superconducting Tokamak (EAST), where n is the toroidal mode number of the applied RMP. It is found that the phase difference between upper RMP coil and lower RMP coil ($ \Delta {\phi }_{{\rm{U}}{\rm{L}}}\left(^\circ\right)={\phi }_{{\rm{U}}}\left(^\circ\right)-{\phi }_{{\rm{L}}}\left(^\circ\right) $ ) is a notable parameter of affecting sawtooth behavior. The experiments for scanning the phase difference$ \Delta {\phi }_{{\rm{U}}{\rm{L}}} $ are carried out. When the phase difference$ \Delta {\phi }_{{\rm{U}}{\rm{L}}} $ of RMP at n = 2 is changed, the sawtooth period and amplitude become subsequently different. The minimum sawtooth period and amplitude appear at$\Delta {\phi }_{{\rm{U}}{\rm{L}}}=270^\circ$ . At the same time, neutron yields measured by neutron diagnostic system have the same trend as sawtooth behavior during RMP phase difference scanning. The plasma response to RMP at n = 2 is analyzed by using the MARS-F code. The results show that the plasma responses much strongly at the$\Delta {\phi }_{{\rm{U}}{\rm{L}}}=270^\circ$ . The loss of fast ion, caused by RMP coils, is possibly stronger at the$\Delta {\phi }_{{\rm{U}}{\rm{L}}}=270^\circ$ than that at other phase difference$ \Delta {\phi }_{{\rm{U}}{\rm{L}}}. $ The loss of fast ion can reduces its stabilization effect on sawtooth behavior, which results in the reduction of the sawtooth period and amplitude. Further research is needed to optimize the sawtooth control method with RMP to make it compatible with plasma performance.-
Keywords:
- experimental advanced superconducting Tokamak /
- resonant magnetic perturbation /
- sawtooth oscillations
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图 2 EAST #116507炮放电中等离子体主要参数的演化 (a)中性束注入功率; (b) n = 2的RMP电流(蓝色)及其上下线圈相位差(红色); (c)锯齿周期(蓝色圆圈)和崩塌幅度(黑色三角); (d)芯部SXR辐射信号; (e)图(d)的局部放大图
Fig. 2. Evolution of plasma parameters for EAST shot #116507: (a) NBI heating power; (b) n = 2 RMP coil current amplitude (blue) and the phase difference between the upper and lower coil
$\Delta {\phi }_{{\rm{U}}{\rm{L}}}$ (red); (c) sawtooth period (blue circles) and amplitude (black triangles); (d) core SXR emission; (e) partial enlargement of panel (d).图 5 EAST #116507炮放电中等离子体参数的演变 (a)芯部SXR辐射信号(蓝色)和RMP上下线圈相位差(红色); (b)锯齿周期(蓝色圆圈)和崩塌幅度(黑色三角); (c)中子产额; (d)等离子体芯部旋转速度
Fig. 5. Evolution of plasma parameters of EAST shot #116507: (a) Core SXR emission (blue) and the phase difference between the upper and lower coil
$\Delta {\phi }_{{\rm{U}}{\rm{L}}}$ of RMP at n = 2 (red); (b) sawtooth period (blue circles) and amplitude (black triangles); (c) neutron yield; (d) toroidal rotation velocity of plasma core.图 6 IRMP = 3.5 kA时, EAST 四炮等离子体参数的演变(a)等离子体电流; (b)中性束注入功率; (c)等离子体密度; (d) n = 2 的RMP上下线圈相位差; (e)中子产额
Fig. 6. Evolution of plasma parameters of four shot with EAST at IRMP = 3.5 kA: (a) Plasma current; (b) NBI heating power; (c) electron density; (d) phase difference between the upper and lower coil
$\Delta {\phi }_{{\rm{U}}{\rm{L}}}$ of RMP at n = 2; (e) neutron yield.图 8 EAST #116507炮放电中n = 2的扰动场在不同相位差下的谱型对比 (a)
$\Delta {\phi }_{{\rm{U}}{\rm{L}}}=0^\circ$ ; (b)$\Delta {\phi }_{{\rm{U}}{\rm{L}}}=180^\circ$ ; (c)$\Delta {\phi }_{{\rm{U}}{\rm{L}}}= 270^\circ$ Fig. 8. Comparison of n = 2 RMP spectrum for different phase difference of discharge #116507: (a)
$\Delta {\phi }_{{\rm{U}}{\rm{L}}}=0^\circ$ ; (b)$\Delta {\phi }_{{\rm{U}}{\rm{L}}}= $ $ 180^\circ$ ; (c)${\Delta }{\phi }_{{\rm{U}}{\rm{L}}}=270^\circ$ . -
[1] Porcelli F, Boucher D, Rosenbluth M N 1996 Plasma Phys. Controlled Fusion 38 2163
Google Scholar
[2] Goniche M, Dumont R J, Bobkov V, et al. 2017 Plasma Phys. Controlled Fusion 59 055001
Google Scholar
[3] Bando T, Wakatsuki T, Honda M, Isayama A, Shinohara K, Inoue S, Yoshida M, Matsunaga G, Takechi M, Oyama N, Ide S 2021 Plasma Phys. Controlled Fusion 63 085009
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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