Conceptual Design of Neutral Beam Injection System for EAST
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Graphical Abstract
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Abstract
Two Neutral Beam Injection (NBI) system will be constructed on the Experimental Advanced Superconducting Tokamak (EAST) in two stages for high power auxiliary plasmas heating and non-inductive current driver. Each NBI can deliver 2~4 MW beam power with 50~80 keV beam energy in 10~100 s pulse length. Each elements of the NBI system are presented in this contribution.
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