导线
大型螺旋装置
电磁线圈
导电体
材料科学
聚变能
螺线管
磁场
超导电性
电流(流体)
核工程
电流密度
渗透(认知心理学)
高温超导
热核聚变
等离子体
电气工程
凝聚态物理
物理
复合材料
核物理学
神经科学
工程类
生物
量子力学
作者
Y. Terazaki,N. Yanagi,Satoshi Ito,Y. Seino,S. Hamaguchi,H. Tamura,T. Mito,Hidetoshi Hashizume,A. Sagara
标识
DOI:10.1109/tasc.2014.2377793
摘要
Based on the successful plasma experiments in the Large Helical Device (LHD), design activities of the LHD-type helical fusion reactor FFHR-d1 are progressing at National Institute for Fusion Science (NIFS). A 100 kA current capacity is required for the winding conductor under the maximum magnetic field of ~12 T. The high-temperature superconductor (HTS) is a promising option for the helical coil conductor. For the development of such a HTS conductor suitable for the helical fusion reactor, we fabricated 30 kA-class HTS conductor samples, and the excitation tests were successfully carried out. We then fabricated and tested a 100-kA class HTS conductor. The conductor sample is a one-turn short-circuit coil with a race-track shape having a bridge-type mechanical lap joint. The transport current of the sample was induced by changing the external magnetic field, then the critical current of the sample was measured. A numerical analysis of the critical current is being performed by self-consistently solving the spatial distributions of the current density and magnetic field among the simply-stacked HTS tapes to verify the measured critical current of the samples. The critical current characteristics of a single HTS tape is evaluated by the percolation model in the precise analysis.
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