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A Research Program of Spherical Tokamak in China 被引量:6

A Research Program of Spherical Tokamak in China
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摘要 The mission of this program is to explore the spherical torus plasma with a SUNIST spherical tokamak. Main experiments in the start phase will be involved with breakdown and plasma current set-up with a mode of saving volt-second and without ohmic heating system, equilibrium and instability, current driving, heating and profile modification. The SUNIST is a university-scale conceptual spherical tokamak, with R = 0.3 m, A 1.3, Ip - 50 kA, BT < 0.15 T, and PRF - 100 kW. The only peculiarity of SUNIST is that there is a toroidal insulating break along the outer wall of vacuum vessel. The expected that advantages of this arrangement are helpful not only for saving flux swing, but also for having a deep understanding of what will influence the discharge startup and globe performances of plasma under different conditions of strong vessel eddy and ECR power assistance. Of course, the vessel structure of cross seal will be at a great risk of controlling vacuum quality, although we have achieved positive results on simulation test and vacuum vessel test. The mission of this program is to explore the spherical torus plasma with a SUNIST spherical tokamak. Main experiments in the start phase will be involved with breakdown and plasma current set-up with a mode of saving volt-second and without ohmic heating system, equilibrium and instability, current driving, heating and profile modification. The SUNIST is a university-scale conceptual spherical tokamak, with R = 0.3 m, A 1.3, Ip - 50 kA, BT < 0.15 T, and PRF - 100 kW. The only peculiarity of SUNIST is that there is a toroidal insulating break along the outer wall of vacuum vessel. The expected that advantages of this arrangement are helpful not only for saving flux swing, but also for having a deep understanding of what will influence the discharge startup and globe performances of plasma under different conditions of strong vessel eddy and ECR power assistance. Of course, the vessel structure of cross seal will be at a great risk of controlling vacuum quality, although we have achieved positive results on simulation test and vacuum vessel test.
作者 何也熙
出处 《Plasma Science and Technology》 SCIE EI CAS CSCD 2002年第4期1355-1363,共9页 等离子体科学和技术(英文版)
基金 This work was supported by National Science Foundation of China No.19889506,Subject Derelopment Priject of TsinghuaUniversity,Innoration Fund of Institute of Physics,Chinese Academy of Science.
关键词 spherical tokamak research program spherical tokamak, research program
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  • 1[1]WAN Yuan-xi. Nuclear Fusion, 2000, 40(6): 1057
  • 2[2]Engelmann F. Nuclear Fusion, 2000, 40(6): 1030
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