Impact of Indentation on the Critical Current of Bi2212 Round Wire
Impact of Indentation on the Critical Current of Bi2212 Round Wire
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DOI：
10.1109/tasc.2016.2532324
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发表时间：
2016-02
影响因子：
1.8
通讯作者：
J. Qin;C. Dai;Qiuliang Wang;Peihang Liu;Bo Liu;Fang Liu;Yu Wu;Chao Zhou;Q. Hao;Chen-shan Li;Sheng Liu
中科院分区：
文献类型：
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作者：
J. Qin;C. Dai;Qiuliang Wang;Peihang Liu;Bo Liu;Fang Liu;Yu Wu;Chao Zhou;Q. Hao;Chen-shan Li;Sheng Liu
CFETR，“中国聚变工程试验堆”，是一个新的托卡马克装置。它的磁体系统包括环向场（TF）、中心螺线管（CS）和极向场线圈。该项目的主要目标是建造一座聚变功率为50-200 MW、包层自给自足的聚变工程托克马克反应堆。CS和TF的最大磁场将达到16 T左右，这远远高于其他反应堆。新材料可用于开发下一代聚变反应堆的磁体技术。Bi_2Sr_2CaCu_2Ox被认为是一种潜在的材料。而Bi-2212相较脆，且圆丝（RW）的外皮为塑性高、强度低的Ag/Ag-Mg合金。在布线或导体制造过程中，导线不可避免地会受到压缩，这可能会导致导线严重压痕。为了研究压痕对Bi-2212临界电流的影响，制作了人工压痕线，并测量了Ic。结果表明，与Nb 3Sn和NbTi线不同，Bi-2212 RW的Ic随着压痕深度的增加而线性下降。研究结果可为Bi-2212导体的设计和制造提供参考。
CFETR, “China Fusion Engineering Test Reactor,” is a new tokamak device. Its magnet system includes the toroidal field (TF), central solenoid (CS), and poloidal field coils. The main goal of this project is to build a fusion engineering tokamak reactor with fusion power of 50-200 MW and self-sufficiency by blanket. The maximum field of CS and TF will get around 16 T, which is much higher than that of other reactors. New materials could be used to develop the technology of magnet for the next generation of fusion reactors. Bi2Sr2CaCu2Ox as a potential material is considered. However, the Bi-2212 phase is brittle, and the sheath of the round wire (RW) is Ag/Ag-Mg alloy with high plasticity and low strength. During cabling or conductor manufacturing, the compression on wire is inevitable, which could cause severe indentation on wire. With the aim of investigating the impact of indentations on the critical current of Bi-2212, the artificially indented wires were made, and Ic was measured. The results show that Ic of a Bi-2212 RW, unlike Nb3Sn and NbTi wires, linearly decreased by the increased depth of indentation. The results are foreseen to be useful for Bi-2212 conductor design and manufacturing.