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Conceptual Design of Neutral Beam Injection System for EAST 被引量:18

Conceptual Design of Neutral Beam Injection System for EAST
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摘要 Neutral beam injection (NBI) system with two neutral beam injections will be con- structed on the Experimental Advanced Superconducting Tokamak (EAST) in two stages for high power auxiliary plasmas heating and non-inductive current drive. 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. Neutral beam injection (NBI) system with two neutral beam injections will be con- structed on the Experimental Advanced Superconducting Tokamak (EAST) in two stages for high power auxiliary plasmas heating and non-inductive current drive. 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.
出处 《Plasma Science and Technology》 SCIE EI CAS CSCD 2012年第6期567-572,共6页 等离子体科学和技术(英文版)
基金 supported by National Natural Science Foundation of China (No. 11075188) the Chinese Academy of Sciences Knowledge Innovation Project: the study of neutral beam steady-state operation of the key technical and physical problems
关键词 neutral beam injection system TOKAMAK EAST auxiliary heating neutral beam injection system, tokamak, EAST, auxiliary heating
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参考文献19

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同被引文献80

  • 1胡立群,张晓东,姚若河.EAST托卡马克的中性束注入方案[J].核技术,2006,29(2):149-152. 被引量:17
  • 2陈珏铨,朱玉宝,张卫.HT-7超导托卡马克上辐射剂量测量与分析[J].辐射防护,2006,26(2):93-98. 被引量:4
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