Experimental progress of hybrid operational scenario on EAST tokamak
Gao, X.1,2; Zeng, L.2; Wu, M. Q.1,3; Zhang, T.2; Yang, Y.2; Ming, T. F.2; Zhu, X.1,3; Wang, Y. M.2; Liu, H. Q.2; Zang, Q.1,2
刊名NUCLEAR FUSION
2020-10-01
卷号60
关键词EAST high normalized beta fishbone power threshold
ISSN号0029-5515
DOI10.1088/1741-4326/abaa91
通讯作者Wu, M. Q.(wumuquan@szu.edu.cn)
英文摘要Extensive experiments of advanced scenario development, which contribute to the ITER hybrid operational scenario have been carried out on experimental advanced superconducting tokamak (EAST) tokamak recently with the ITER-like tungsten divertor. The beta(N) in this operational scenario is intermediate up to 2.1 (EAST#78987, beta(N) similar to 2.1, I-p similar to 0.45 MA, q(95) = 3.7, B-T similar to 1.5 T, 3 MW neutron beam injection and 1 MW 4.6 GHz lower hybrid wave). In these hybrid H-mode plasmas, the internal transport barrier (ITB) has been frequently observed with central flatqprofile and it is found that the fishbone mode (m/n= 1/1) can be beneficial to sustain the central flat (q(0) similar to 1)qprofile, thus a stable ITB can be obtained. In this case, better plasma performance is achieved. The formation of the ITB of the electron density is related to the fishbone activities. Energy transport analysis shows that the fishbone instabilities have a suppression on electron turbulent energy transport, while the ITB of ion temperature is due to the suppression of high-k modes (electron temperature gradient). The mechanism of turbulence suppression from fishbone instabilities in the EAST tokamak is not clear and needs more investigation. It is also observed that the power threshold for ITB formation is >= 3.5 MW, which is consistent with the scaling law for other tokamaks. The dimensionless parameter G (= H-89 beta(N)/q(95)(2)) obtained in the EAST reaches 0.3, but is still lower than the ITER hybrid scenario design (G >= 0.4) and needs more extension. Further investigation of extending the operational regimes, such as expanding the ITB foot outwards, would be important for the development of the hybrid and steady-state scenarios for next-step fusion devices like ITER and CFETR.
资助项目National Nature Science Foundation of China[11975271] ; National Nature Science Foundation of China[11675211] ; National Nature Science Foundation of China[11905145] ; National Key R&D Program of China[2017YFE0301205] ; National Key R&D Program of China[2017YFE0300500] ; National Key R&D Program of China[2017YFE0300501]
WOS关键词HIGH-PERFORMANCE DISCHARGES ; DIII-D ; HIGH CONFINEMENT ; STATIONARY ; TRANSPORT ; PLASMAS ; TURBULENCE ; FRACTION ; PHYSICS ; SHEAR
WOS研究方向Physics
语种英语
出版者IOP PUBLISHING LTD
WOS记录号WOS:000568352300001
资助机构National Nature Science Foundation of China ; National Key R&D Program of China
内容类型期刊论文
源URL[http://ir.hfcas.ac.cn:8080/handle/334002/104042]  
专题中国科学院合肥物质科学研究院
通讯作者Wu, M. Q.
作者单位1.Shenzhen Univ, Adv Energy Res Ctr, Shenzhen 518060, Peoples R China
2.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China
3.Shenzhen Univ, Coll Optoelect Engn, Key Lab Optoelect Devices & Syst, Minist Educ & Guangdong Prov, Shenzhen 518060, Peoples R China
推荐引用方式
GB/T 7714
Gao, X.,Zeng, L.,Wu, M. Q.,et al. Experimental progress of hybrid operational scenario on EAST tokamak[J]. NUCLEAR FUSION,2020,60.
APA Gao, X..,Zeng, L..,Wu, M. Q..,Zhang, T..,Yang, Y..,...&Wan, Y. X..(2020).Experimental progress of hybrid operational scenario on EAST tokamak.NUCLEAR FUSION,60.
MLA Gao, X.,et al."Experimental progress of hybrid operational scenario on EAST tokamak".NUCLEAR FUSION 60(2020).
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