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First Achievement of Plasma Heating for EAST Neutral Beam Injector 被引量:4

First Achievement of Plasma Heating for EAST Neutral Beam Injector
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摘要 As one of the most effective methods for plasma heating,a neutral beam injector(NBI) achieved plasma heating and current driving for the first time in EAST 2014 experimental campaign.According to the research plan of the EAST physics experiment,the first NBI(EASTNBI-1) has been built and become operational in 2014.In this article,the latest experiment results of EAST-NBI-1 are reported as follows:(1) EAST achieves H-mode plasma in the case of NBI heating alone,(2) EAST achieves 22 s long pulse stable H-mode plasma in the case of sinndtaneous NBI and lower hybrid wave(LHW) heating.The measurement data show that the loop voltage decreased and the plasma stored energy increased obviously.The results indicate that EAST-NBI-1 has achieved plasma heating and current driving,and thus lays a foundation for the construction of EAST-NBI-2,which will be built in a few months this year. As one of the most effective methods for plasma heating,a neutral beam injector(NBI) achieved plasma heating and current driving for the first time in EAST 2014 experimental campaign.According to the research plan of the EAST physics experiment,the first NBI(EASTNBI-1) has been built and become operational in 2014.In this article,the latest experiment results of EAST-NBI-1 are reported as follows:(1) EAST achieves H-mode plasma in the case of NBI heating alone,(2) EAST achieves 22 s long pulse stable H-mode plasma in the case of sinndtaneous NBI and lower hybrid wave(LHW) heating.The measurement data show that the loop voltage decreased and the plasma stored energy increased obviously.The results indicate that EAST-NBI-1 has achieved plasma heating and current driving,and thus lays a foundation for the construction of EAST-NBI-2,which will be built in a few months this year.
作者 胡纯栋
出处 《Plasma Science and Technology》 SCIE EI CAS CSCD 2015年第1期1-3,共3页 等离子体科学和技术(英文版)
基金 supported by the National Magnetic Confinement Fusion Science Program of China(No.2013GB101000)
关键词 neutral beam injector plasma heating current driving neutral beam injector plasma heating current driving
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参考文献7

  • 1Wan Y X, HT-7 Team and HT-7U Team. 2000, Nucl. Fusion, 40:1057.
  • 2Li J G and Wan B N for the EAST Team and Interna- tional Collaborators. 2011, Nucl. Fusion, 51:094007.
  • 3Wan B N for the EAST and HT-7 Teams and Interna- tional Collaborators. 2009, Nuel. ~sion, 49:I04011.
  • 4Xu Y J, Hu C D, Liu S, et al. 2012, Chin. Phys. Lett., 29:035201.
  • 5Hu C D for the NBI Team. 2012, Plasma Sci. Technol 14:871.
  • 6Hu C D, Xie Y H, NBI Team. 2012, Plasma Sci. Tech- nol., 14:75.
  • 7Hu C D and the NBI Team. 2013, Plasma Sci. Tech- nol., 15:201.

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