Effects of divertor geometry on detachment and core plasma performance with impurity seeding in EAST

Divertor detachment operation compatible with the core plasma is an effective method to alleviate the steady-state heat flux approaching the divertor target; this scheme will be adopted by high-performance tokamaks in the future, such as International Thermonuclear Experimental Reactor (ITER). Curre...

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Detalles Bibliográficos

Principais autores:	L.Y. Meng, L. Wang, J.B. Liu, K.D. Li, X. Lin, X.J. Liu, G.Z. Jia, J. Guo, T. He, L. Yu, P.J. Tang, J.C. Xu, W.M. Zhang, L. Zhang, J.J. Yang, Y.M. Duan, F.B. Zhong, T. Zhang, M.R. Wang, Z.C. Lin, T.Q. Jia, B. Zhang, Q. Zang, Y.W. Yu, Z.X. Chen, G.S. Xu, B.N. Wan
Formato:	Artigo
Idioma:	Inglês
Publicado:	IOP Publishing 2024-01-01
Series:	Nuclear Fusion
Assuntos:	divertor geometry detachment compatibility EAST
Acceso en liña:	https://doi.org/10.1088/1741-4326/ad80aa
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