摘要
The neutral beam injection （NBI） system was developed on the Experimental Ad- vanced Superconducting Tokamak （EAST） for plasma heating and current driving. This paper presents the brief history, design, development, and the main experimental results of the R＆D of neutral beam injector on the test bed and on EAST. In particular, it will describe： （1） how the two beamlines with a total beam power of 8 MW were developed; （2） the design of the EAST-NBI system including the high power ion source, main vacuum chamber, inner components, beam diag- nostic system and sub-system; （3） the experimental results of beamline-1 on the summer campaign of EAST in 2014 and, （4） the status of beamline-2 and the future plan of EAST-NBIs.
The neutral beam injection （NBI） system was developed on the Experimental Ad- vanced Superconducting Tokamak （EAST） for plasma heating and current driving. This paper presents the brief history, design, development, and the main experimental results of the R＆D of neutral beam injector on the test bed and on EAST. In particular, it will describe： （1） how the two beamlines with a total beam power of 8 MW were developed; （2） the design of the EAST-NBI system including the high power ion source, main vacuum chamber, inner components, beam diag- nostic system and sub-system; （3） the experimental results of beamline-1 on the summer campaign of EAST in 2014 and, （4） the status of beamline-2 and the future plan of EAST-NBIs.
基金
supported by the National Magnetic Confinement Fusion Science Program of China(No.2013GB101000,Sub-Contract No.2013GB101001)
National Natural Science Foundation of China(No.11405207)
the International Science&Technology Cooperation Program of China(No.2014DFG61950)
