Experimental investigation of lower hybrid current drive induced plasma rotation on the experimental advanced superconducting tokamak

Yang Jin; Chen Jun; Wang Fu-Di; Li Ying-Ying; Lyu Bo; Xiang Dong; Yin Xiang-Hui; Zhang Hong-Ming; Fu Jia; Liu Hai-Qing; Zang Qing; Chu Yu-Qi; Liu Jian-Wen; Wang Xun-Yu; Bin Bin; He Liang; Wan Shun-Kuan; Gong Xue-Yu; Ye Min-You

doi:10.7498/aps.69.20191716

Abstract

Rotation and its shear can reduce the magnetohydrodynamic instabilities and enhance the confinement. The LHCD has been proposed as a possible means of rotation driving on a future fusion reactor. Exploring the mechanisms of LHCD rotation driving on the current tokamaks can provide important reference for future reactors. On EAST, it was previously shown that 2.45 GHz LHCD can drive plasma toroidal rotation and the change of edge plasma rotation leads the co-current core rotation to increase. At higher frequency, 4.6 GHz lower hybrid wave can more effectively drive co-current plasma toroidal rotation. On EAST, at the lower current, the effects of different LHCD power on plasma toroidal rotation are analyzed. Higher power LHCD has a better driving efficiency. The effect of safety factor (q) profile on toroidal rotation is also presented. The LHCD can change the profile of safety factor due to current drive. It is found that when the power exceeds 1.4MW, the q profile remains unchanged and the rotation changes only very slightly with LHCD power, suggesting that the current profile is closely related to rotation. In order to further analyze the dynamic process of plasma toroidal rotation driven by lower hybrid current drive on EAST, the toroidal momentum transport due to LHCD is deduced by using the modulated LHCD power injection. Based on the momentum balance equation, the toroidal momentum diffusion coefficient (χ_φ) and the toroidal momentum pinch coefficient (V_pinch) are obtained by the method of separation of variables and Fourier analysis for the region where the external momentum source can be ignored. It is found that the momentum diffusion coefficient (χ_φ) and momentum pinch coefficient (V_pinch) tend to increase from the core to the outer region. This is consistent with the characteristic that the toroidal rotation velocity first changes in the outer region and then propagates to the core when the toroidal rotation is driven by LHCD.

Keywords:

Authors and contacts

1.
School of Nuclear Science and Technology, University of South China, Hengyang 421001, China
2.
Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China
3.
Department of Engineering and Applied Physics, University of Science and Technology of China, Hefei 230026, China
4.
School of Electrical Engineering, University of South China, Hengyang 421001, China

Corresponding author: Lyu Bo, blu@ipp.ac.cn ; Xiang Dong, xiangdong007@163.com ;

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References

[1]	Betti R, Freidberg J P 1995 Phys. Rev. Lett. 74 2949 Google Scholar
[2]	Rice J E, Podpaly Y A, Reinke M L, Gao C, Shiraiwa S, Terry J L, Theiler C, Wallace G M, Bonoli P T, Brunner D 2013 Nucl. Fusion. 53 093015 Google Scholar
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Cited By

图 1 典型参数随时间变化的波形图 (#70938)　(a) 等离子体电流 (黑色), 低杂波功率 (蓝色); (b) 环电压 (黑色)和内感 (蓝色); (c) 芯部弦平均电子密度; (d) 储能; (e) 芯部电子温度 (黑色)和芯部离子温度 (红色); (f) 芯部环向速度变化

Figure 1. Waveforms of typical parameters of an LHCD shot (#70938) on EAST: (a) Plasma current (black) and LHCD power)(blue); (b) loop voltage (black) and internal inductance (blue); (c) central line averaged electron density; (d) stored energy; (e) central ion (red) and electron (black) temperature; (f) the change of core toroidal rotation velocity.

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图 2 不同低杂波功率下典型参数随时间变化的波形图　(a) 等离子体电流; (b) 芯部弦平均电子密度; (c) 低杂波功率; (d) 芯部环向旋转速度变化

Figure 2. Waveforms of typical parameters at different LHCD power levels: (a) plasma current; (b) central line averaged electron density; (c) LHCD power; (d) the change of core toroidal rotation velocity.

DownLoad: Full-Size Img PowerPoint

图 3 低杂波功率与芯部环向旋转速度变化关系

Figure 3. The relationship between the change of core toroidal rotation velocity and LHCD power.

DownLoad: Full-Size Img PowerPoint

图 4 不同低杂波驱动功率下安全因子剖面

Figure 4. Profiles of safety factor at different LHCD powers.

DownLoad: Full-Size Img PowerPoint

图 5 典型参数随时间变化的波形图　(a) 电子温度; (b) 离子温度; (c) 环向旋转速度对调制束的响应; (d) LHCD功率(黑色)和芯部弦平均电子密度(蓝色)

Figure 5. Waveforms of typical parameters: (a) Electron temperature; (b) ion temperature; (c) toroidal rotation velocity; (d) LHCD power (black) and central line averaged electron density (blue).

DownLoad: Full-Size Img PowerPoint

图 6 (a) 环向速度调制幅度(V_t0)的剖面图; (b) 环向速度相位变换(φ)的剖面图

Figure 6. (a) Profile of toroidal velocity modulation amplitude; (b) profile of toroidal velocity phase transformation.

DownLoad: Full-Size Img PowerPoint

图 7 (a) 环向动量扩散系数(χ_φ) 的剖面图; (b) 箍缩系数(V_pinch)的剖面图

Figure 7. (a) Profile of toroidal momentum diffusion coefficient; (b) profile of toroidal momentum pinch coefficient.

DownLoad: Full-Size Img PowerPoint

[1]	Betti R, Freidberg J P 1995 Phys. Rev. Lett. 74 2949 Google Scholar
[2]	Rice J E, Podpaly Y A, Reinke M L, Gao C, Shiraiwa S, Terry J L, Theiler C, Wallace G M, Bonoli P T, Brunner D 2013 Nucl. Fusion. 53 093015 Google Scholar
[3]	Rice J E, Gao C, Mumgaard R, et al. 2016 Nucl. Fusion. 56 036015 Google Scholar
[4]	Chouli B, Fenzi C, Garbet X, et al. 2014 Plasma Phys. Controlled Fusion. 56 095018 Google Scholar
[5]	Chouli B, Fenzi C, Garbet X, Bourdelle C, Sarazin Y, Rice J, Aniel T, Artaud J F, Baiocchi B, Basiuk V, Cottier P, Decker J, Imbeaux F, Irishkin M, Mazon D, Schneider M, the Tore Supra Team 2015 Plasma Phys. Controlled Fusion. 57 125007 Google Scholar
[6]	Shi Y, Xu G, Wang F, Wang M, Fu J, Li Y, Zhang W, Chang J, Lv B, Qian J, Shan J, Liu F, Ding S, Wan B, Lee S G, Bitter M, Hill K 2011 Phys. Rev. Lett. 106 235001 Google Scholar
[7]	Yin X H, Chen J, Hu R J, Yi Y Y, Wang F D, Fu J, Ding B J, Wang M, Liu F K, Zang Q, Shi Y J, Lyu B, Wan B N, the EAST team 2017 Chin. Phys. B 26 115203 Google Scholar
[8]	Koide Y, Tuda T, Ushigusa K, Asakura N, Sakasai A, Ide S, Ishida S, Kikuchi M, Azumi M, Funahashi A 1992 Plasma Phys. Control. Nucl. Fusion. Res. 1 777
[9]	Eriksson L G, Hellsten T, Nave F, Brzozowski J, Holmström K, Johnson T, Ongena J, Zastrow K D 2009 Plasma Phys. Controlled Fusion. 51 044008 Google Scholar
[10]	Nave M F F, Kirov K, Bernardo J, Brix M, Ferreira J, Giroud C, Hawkes N, Hellsten T, Jonsson T, Mailloux J, Ongena J, Parra F, JET Contributors 2017 Nucl. Fusion. 57 034002 Google Scholar
[11]	Wan B N, Liang Y F, Gong X Z, Li J G, Xiang N, Xu G S, Sun Y W, Wang L, Qian J P, Liu H Q, Zhang X D, Hu L Q, Hu J S, Liu F K, Hu C D, Zhao Y P, Zeng L, Wang M, Xu H D, Luo G N 2017 Nucl. Fusion. 57 102019 Google Scholar
[12]	Ding B J, Li Y C, Zhang L, et al. 2015 Nucl. Fusion. 55 093030 Google Scholar
[13]	Lyu B, Wang F D, Pan X Y, et al. 2014 Rev. Sci. Instruments. 85 11E406 Google Scholar
[14]	Lyu B, Chen J, Hu R J, et al. 2016 Rev. Sci. Instruments. 87 11E326 Google Scholar
[15]	Lyu B, Chen J, Hu R J, et al. 2018 Rev. Sci. Instruments. 89 10F112 Google Scholar
[16]	Li Y Y, Fu J, Lyu B, Du X W, Li C Y, Zhang Y, Yin X H, Yu Y, Wang Q P, von Hellermann M 2014 Rev. Sci. Instruments. 85 11E428 Google Scholar
[17]	Rice J E, Ince-Cushman A, deGrassie J S, Eriksson L G, Sakamoto Y, Scarabosio A, Bortolon A, Burrell K H, Duval B P, Fenzi-Bonizec C, Greenwald M J, Groebner R J, Hoang G T, Koide Y, Marmar E S, Pochelon A, Podpaly Y 2007 Nucl. Fusion. 47 1618 Google Scholar
[18]	Liu H Q, Qian J P, Jie Y X, et al. 2016 Rev. Sci. Instruments. 87 11D903 Google Scholar
[19]	Yoshida M, Koide Y, Takenaga H, Urano H, Oyama N, Kamiya K, Sakamoto Y, Kamada Y and the JT-60 Team 2006 Plasma Phys. Control. Fusion. 48 1673 Google Scholar
[20]	Yoshida M, Koide Y, Takenaga H, Urano H, Oyama N, Kamiya K, Sakamoto Y, Matsunaga G, Kamada Y and the JT-60U Team 2007 Nucl. Fusion. 47 856 Google Scholar
[21]	Ida K, Miura Y, Itoh K, Itoh S I, Matsuda T 1998 J. Phys. Soc. Japan. 67 4089 Google Scholar

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Vol. 69, Issue 5 - 2020-03-05

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