I-mode operation in helium plasma with pure radio frequency wave heating and ITER-like tungsten divertor on EAST
I-mode operation in helium plasma with pure radio frequency wave heating and ITER-like tungsten divertor on EAST
复制标题
EAST 上采用纯射频波加热和类似 ITER 的钨偏滤器在氦等离子体中进行 I 模式操作
DOI：
10.1088/1741-4326/ac207d
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发表时间：
2021
期刊：
影响因子：
3.3
通讯作者：
L. Zhang
中科院分区：
文献类型：
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作者：
B. Zhang;X. Gong;J. Qian;R. Ding;J. Huang;X. Zou;A. Liu;X. Zhong;C. Zhou;J.Y. Zhang;T. Jia;R. Liang;W. Gao;G. Zhong;L. Zeng;T. Zhang;H.Q. Liu;Q. Zang;Y. Duan;L.Q. Xu;T. Zhou;E. Li;M.H. Li;H.D. Xu;B. Ding;Y. Song;X.J. Zhang;C. Qin;X.J. Wang;B. Lyu;L. Wang;L. Zhang
在EAST上首次研究了在B T位形下，射频加热氦等离子体和类ITER钨偏滤器的I模运转特性。在注入总功率为3.5 MW时，在I p = 0.5 MA，B T = 2.4 T的条件下，获得了持续时间约为5.4 s的稳定I模，沿着出现了30-90 kHz的弱相干模和约13 kHz的边缘温度环振荡。脉冲长度仅受加热功率持续时间的限制。发现He浓度在I模操作中起关键作用，因为随着He浓度的增加，L-I跃迁阈值功率增加，能量约束降低。给出了在相似He浓度下，I模和H模等离子体之间的能量约束和偏滤器热流的实验研究结果。
The characteristics of I-mode operation in helium (He) plasma with radio-frequency (RF) wave heating and ITER-like tungsten divertor have been investigated for the first time on EAST, under the favorable B T configuration. Stationary I-mode in He plasma lasting for ∼5.4 s was achieved at I p = 0.5 MA, B T = 2.4 T with a total injected RF power of 3.5 MW, along with the appearance of the 30–90 kHz weakly coherent mode and the ∼13 kHz edge temperature ring oscillation. The pulse length was only limited by the heating power duration. He concentration was found to play a critical role in I-mode operation, as L–I transition threshold power was increased and the energy confinement was degraded with increasing He concentration. The experimental investigation result on energy confinement and divertor heat flux between I- and H-mode plasma was also given at a similar He concentration.