摘要
EAST(Experimental Advanced Superconducting Tokamak)作为世界上第一个全超导非圆截面托克马克,其目标是研究1 000 s的长脉冲稳态运行的前沿性物理问题,要达成这一目标,必须有高功率电流驱动和辅助加热系统以实现EAST装置的高参数稳态运行。中性束注入(Neutral Beam Injection,NBI)加热是等离子体辅助加热和维持最有效的手段之一,为此一套注入功率4–8 MW、脉冲宽度10–100 s的中性束注入系统于2010年开工建设,并于2014年实现了对等离子体的加热和驱动。本文主要展示了EAST中性束注入器的最新进展,从长脉冲束引出和高功率束引出两个方面介绍了EAST中性束注入器综合测试台的最新实验结果,结果表明在束功率和脉冲宽度方面已经达到或超过设计指标。
Background： As the first full superconducting non-circular cross section Tokomak in the world, Experimental Advanced Superconducting Tokamak （EAST） is used to explore the forefront physics and engineering issues on the construction of Tokomak fusion reactor. Neutral beam injection has been recognized as one of the most effective means for plasma heating.Purpose： This paper aims to present the latest progresses of EAST neutral beam injector.Methods：Long pulse beam extraction and high power beam extraction were experimentally tested to verify the performance of a set of neutral beam injectors （4–8 MW, 10–100 s） which were developed and put into operation in 2014.Results： Test results showed that beam power and pulse length met or exceeded the design requirments. Conclusion： All these progresses lay a solid foundation for the achievement of plasma heating and current drive for EAST in the future.
出处
《核技术》
CAS
CSCD
北大核心
2015年第11期91-94,共4页
Nuclear Techniques
基金
国家磁约束核聚变能发展研究专项(No.2013GB101001)资助
关键词
中性束注入器
束引出
离子源
Neutral beam injector
Beam extraction
Ion source
