Electrical joints are critical components of the PF coil in the tokamak, serving as all electric and coolant transfer between adjacent conductors. The technologies and tooling used for joint manufacture are great chal...Electrical joints are critical components of the PF coil in the tokamak, serving as all electric and coolant transfer between adjacent conductors. The technologies and tooling used for joint manufacture are great challenges in coil fabrication, including termination box and cover manufacturing, jacket removal of the conductor, petals drawing apart and reformation, nickel coating removal and tin plating on the cable, compaction of the cable into the termination, final machining of the termination, etc. This paper mainly focuses on the solution of technical issues, based on previous R＆：D activities of joint. Meanwhile, a detailed mamffacture plan has been confirmed. The technologies and tooling also can be used as reference for the electrical joint manufacture for PF coils and other large-scale coils.展开更多
The Chinese Fusion Engineering Test Reactor(CFETR)represents the next generation of full superconducting fusion reactors in China.Recently,CFETR was redesigned with a larger size and will be operated in two phases.To ...The Chinese Fusion Engineering Test Reactor(CFETR)represents the next generation of full superconducting fusion reactors in China.Recently,CFETR was redesigned with a larger size and will be operated in two phases.To reduce the heat flux on the target plate,a snowflake(SF)divertor configuration is proposed.In this paper we show that by adding two dedicated poloidal field(PF)coils,the SF configuration can be achieved in both phases.The equilibria were calculated by TEQ code for a range of self-inductances l_i3.The coil currents were calculated at some fiducial points in the flattop phase.The results indicate that the PF coil system has the ability to maintain a long flattop phase in 7.5 and 10 MA inductive scenarios for the single null divertor(SND)and SF divertor configurations.The properties of the SF configuration were also analyzed.The connection length and flux expansion of the SF divertor were both increased significantly over the SND.展开更多
基金supported by National Natural Science Foundation of China(No.51177164)
文摘Electrical joints are critical components of the PF coil in the tokamak, serving as all electric and coolant transfer between adjacent conductors. The technologies and tooling used for joint manufacture are great challenges in coil fabrication, including termination box and cover manufacturing, jacket removal of the conductor, petals drawing apart and reformation, nickel coating removal and tin plating on the cable, compaction of the cable into the termination, final machining of the termination, etc. This paper mainly focuses on the solution of technical issues, based on previous R＆：D activities of joint. Meanwhile, a detailed mamffacture plan has been confirmed. The technologies and tooling also can be used as reference for the electrical joint manufacture for PF coils and other large-scale coils.
基金supported by the National Magnetic Confinement Fusion Program under grant nos 2014GB106001,2014GB110003 and 2013GB111000National Natural Science Foundation of China under grant no.11675221
文摘The Chinese Fusion Engineering Test Reactor(CFETR)represents the next generation of full superconducting fusion reactors in China.Recently,CFETR was redesigned with a larger size and will be operated in two phases.To reduce the heat flux on the target plate,a snowflake(SF)divertor configuration is proposed.In this paper we show that by adding two dedicated poloidal field(PF)coils,the SF configuration can be achieved in both phases.The equilibria were calculated by TEQ code for a range of self-inductances l_i3.The coil currents were calculated at some fiducial points in the flattop phase.The results indicate that the PF coil system has the ability to maintain a long flattop phase in 7.5 and 10 MA inductive scenarios for the single null divertor(SND)and SF divertor configurations.The properties of the SF configuration were also analyzed.The connection length and flux expansion of the SF divertor were both increased significantly over the SND.
