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Center conductor design for the compact spherical torus reactor

机译:紧凑型球形圆环反应堆的中心导体设计

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The spherical torus (ST) concept has been previously proposed as a means of achieving high plasma beta at low aspect ratio and low magnetic field. The center post performance is presently analyzed as a function of operating time for a representative spherical torus reactor with the following parameters: (1) 2000-MW thermal power; (2) 1.45-m major radius; (3) 1.17-m minor radius (A=1.22); (4) elongation, 2.2; and (5) toroidal field on axis 0.824 T. The key engineering issues for the center post design are the resistive loss, magnet coolant velocity, conductor temperatures, and physical erosion of the magnet by the coolant flow. Specifically, resistive loss can be as high as 111 MW, with peak conductor temperature under 300 degrees C, requiring a peak coolant velocity of approximately 12 m/s.
机译:先前已经提出了球形圆环(ST)概念,作为在低纵横比和低磁场下实现高等离子体β的一种手段。目前,对具有以下参数的代表性球形圆环反应堆的中心柱性能进行分析,其是工作时间的函数:(1)2000兆瓦火力; (2)1.45米长半径; (3)小半径1.17米(A = 1.22); (4)伸长率,2.2; (5)0.824 T轴上的环形磁场。中心柱设计的关键工程问题是电阻损耗,磁体冷却剂速度,导体温度以及冷却剂流对磁体的物理腐蚀。具体而言,在导体的峰值温度低于300摄氏度时,电阻损耗可能高达111 MW,从而需要约12 m / s的峰值冷却剂速度。

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