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Design and Operation of a Load-Tolerant ICRH System in Experimental Advanced Superconducting Tokamak

L. N. Liu,X. J. Zhang,C. M. Qin,Y. Z. Mao,S. Yuan,W. Zhang,H. Yang,L. Wang,Y. Cheng,K. Zhang

Nuclear Fusion（2024）

Cited 0|Views29
Key words
load-tolerant,EAST,ICRH system,plasma heating
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