Superconducting magnet system for the TPX Tokamak

Magnetics, IEEE Transactions  (1994)

引用 5|浏览15
暂无评分
摘要
The Tokamak Physics Experiment (TPX) will be the first Tokamak using superconducting magnets for both the poloidal and toroidal field. It is designed for advanced Tokamak physics experiments in steady-state and long-pulse operation. The TPX superconducting magnets use an advanced cable-in-conduit conductor (CICC) design similar to that developed in support of the International Thermonuclear Experimental Reactor (ITER). The toroidal field magnets provide 4.0 T at 2.25 m with a stored energy of 1.05 GJ. The poloidal field magnets provide 18.0 V-s to ohmically start and control long burns of a 2.0 MA plasma
更多
查看译文
关键词
Tokamak devices,fusion reactor theory and design,superconducting magnets,1.05 GJ,2.25 m,4 T,TPX tokamak,cable-in-conduit conductor,poloidal field magnets,superconducting magnets,toroidal field magnets
AI 理解论文
溯源树
样例
生成溯源树,研究论文发展脉络
Chat Paper
正在生成论文摘要