Progress of the CFETR design
作者: G. ZhuangG.Q. LiJ. LiY.X. WanY. LiuX.L. WangY.T. SongV. ChanQ.W. YangB.N. WanX.R. DuanP. FuB.J. Xiaothe CFETR Design Team
作者单位: 1University of Science and Technology of China, Hefei 230026, People’s Republic of China
2Institutes of Plasma Physics, CAS, Hefei 230031, People’s Republic of China
3Southwest Institute of Physics, Chengdu 610041, People’s Republic of China
4China Academy of Engineering Physics, Mianyangc 621900, People’s Republic of China
5General Atomic, San Diego, CA, United States of America
刊名: Nuclear Fusion, 2019, Vol.59 (11)
来源数据库: Institute of Physics Journal
DOI: 10.1088/1741-4326/ab0e27
原始语种摘要: The Chinese Fusion Engineering Testing Reactor (CFETR), complementing the ITER facility, is aiming to demonstrate fusion energy production up to 200 MW initially and to eventually reach DEMO relevant power level 1 GW, to manifest a high duty factor of 0.3–0.5, and to pursue tritium self-sufficiency with tritium breeding ratio (TBR) >1. The key challenge to meet the missions of the CFETR is to run the machine in steady state (or long pulse) and high duty factor. By using a multi-dimensional code suite with physics-based models, self-consistent steady-state and hybrid mode scenarios for CFETR have been developed under a high magnetic field up to 6.5 T. The negative-ion neutral beam injection together with high frequency electron cyclotron wave and lower hybrid wave (and/or fast wave) are...
全文获取路径: IOP 

  • design 设计
  • system 
  • tritium 
  • development 开发
  • proposed 建议的
  • reach 河区
  • together 共同
  • level 水准
  • developed 开发
  • complementing 求反运算