Analysis of strain distribution and critical current of superconductors based on a strain-critical current measurement system

Abstract

Abstract:

Based on Pacman device which is widely used to investigate the axial strain dependence of the critical current in superconductors, the finite element analysis method is employed to carry out the force analysis of the spring and the superconducting strand, thereby the axial and lateral strain distributions of the superconducting strand are obtained. According to the two extreme assumptions (low inter-filament resistance and high inter-filament resistance), the effects of the strain homogeneity at the cross section of the superconductor on the critical current is analyzed combined with the Nb₃Sn deviatoric strain-critical current scaling law.

Key words: Strain, Critical current, Finite element, Inter-filament resistance

摘要：

基于当前应用较广泛的应变下临界电流测量装置Pacman，利用有限元方法对应变盘及超导线进行受力分析，得到了超导线轴向及横向的应变分布情况。结合Nb₃Sn超导线偏应变临界电流定标律，分析了在两种极限假设情况(低丝间电阻和高丝间电阻)下超导线截面应变分布对临界电流的影响。

关键词: 应变, 临界电流, 有限元, 丝间电阻

CLC Number:

O511.4

LIU Fang, WU Yu, LONG Feng. Analysis of strain distribution and critical current of superconductors based on a strain-critical current measurement system[J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2010, 30(4): 355-359.

刘方，武玉，龙风. 应变-临界电流测量系统中超导线应变分布及临界电流分析[J]. 核聚变与等离子体物理, 2010, 30(4): 355-359.

References

[1] Ekin J W. Strain scaling law for flux pinning in practical superconductors. Part 1: basic relationship and appli- cation to Nb₃Sn conductors [J]. Cryogenics, 1980, 20(11): 611-624.

[2] David M J Taylor, Damian P Hampshire. Properties of helical springs used to measure the axial strain dependence of the critical current density in superconducting wires[J]. Supercond. Sci. Techn., 2005, 18: 356-368.

[3] Godeke A, Dhallé, Morelli M M J, et al.A device to investigate the axial strain dependence of the critical current density in superconductors[J]. Rev. Sci. Instrum., 2004, 75(12): 5112-5118.

[4] Yoshihiko Nunoya, Takaaki Isono. Development of strain-applying apparatus for evaluation of ITER Nb₃Sn strand[J]. IEEE Transactions on applied super- conductivity, 2007, 17(2): 2588-2590.

[5] 刘方. ITER用超导股线性能分析与研究[D]. 合肥: 中科院合肥物质科学研究院, 2008.

[6] Godeke A. Performance boundaries in Nb₃Sn super- conductors[D]. Netherlands: University of Twente, 2005.

[7] Van N C den Eijnden, Nijhuis A. Axial tensile stress- strain characterization of ITER model coil type Nb₃Sn strands in TARSIS[J]. Supercond. Sci. Techn., 2005, 18: 1523-1532.

[8] Ekin J W. Strain scaling law and the prediction of uniaxial and bending strain effects in multifilamentary superconductors[A]. Masaki Suenaga and Alan F. Clark, Proc. Topical Conf. on-A15-Supercond[C]. New York: Pleum publishing corporation, 1980, 187.

[9] Ilyin Y, Nijhuis A, Krooshoop E. Scaling law for the strain dependence of the critical current in an advanced ITER Nb₃Sn strand[J]. Supercond. Sci. Techn., 2007, 20: 186-191.

[10] Nijhuis A, N C van den Eijnden, Y Ilyin, et al. Impact of spatial periodic bending and load cycling on the critical current of a Nb₃Sn strand[J]. Supercond. Sci. techn., 2005, 18: S273-283.

[11] Nijhuis A, Y llyin, WA J Wessel, at el. Critical current and strand stiffness of three types of Nb₃Sn strand subjected to spatial periodic bending[J]. Supercond. Sci. Techn., 2006, 19: 1136–1145.

[12] Corato V, Muzzi L, U Besi Vetrella, at el. Direct measurement of interfilament resistance in Nb₃Sn strands[J]. Journal of Applied Physics, 2009, 105: 093930-1- 093930-5.

[1]	ZOU Chun-long, LIU Xu-feng, DU Shuang-song. Analysis of critical current degradation of CICC superconducting joint under cyclic force load [J]. Nuclear Fusion and Plasma Physics, 2025, 45(1): 45-48.
[2]	ZHANG Xiao-qiang, LU Bi-wei, LIU Jia-qin, SUN Fei, WU Yu-cheng. Numerical simulation analysis of the heat exchange of W/Cu module in the divertor [J]. Nuclear Fusion and Plasma Physics, 2024, 44(2): 133-140.
[3]	QU Miao, YAN Sha. Study on dependence of tungsten primary crack on pulse width time under transient heat flow [J]. Nuclear Fusion and Plasma Physics, 2024, 44(2): 206-213.
[4]	ZHANG Yong, WU Jie-feng, Liu Song-lin , LEI Ming-zhun , WANG Wan-jing , MA Jian-guo. Simulation analysis on the first wall electron beam welding of water cooled ceramic breeder blanket [J]. Nuclear Fusion and Plasma Physics, 2023, 43(3): 290-297.
[5]	YANG Yin, JIANG Tao, XIA Zhi-wei . Structure analysis and optimization of gas injection pipeline in tokamak [J]. Nuclear Fusion and Plasma Physics, 2023, 43(2): 185-190.
[6]	GONG Zheng, HAN Song-bo , NI Xiao-jun , GE Jian , HUANG Jian-jun , YU Bin, GAO Xiang, SUN Jin-xing. Structural stability analysis of CFETR vacuum vessel based on finite element method [J]. Nuclear Fusion and Plasma Physics, 2023, 43(1): 38-42.
[7]	SHEN Jian-xia, LI Zhu-yong, XI Dong-min, ZHANG Long, SONG Meng, XIA Ya-jun. Effects of narrow-stacked wires with different stacking structure on critical current for an HTS cable-in-conduit conductor [J]. Nuclear Fusion and Plasma Physics, 2022, 42(s1): 108-113.
[8]	LIANG Han-yu, SHENG Jie . Optimization of the magnets of a compact high temperature superconducting tokamak based on genetic algorithm [J]. Nuclear Fusion and Plasma Physics, 2022, 42(s1): 120-124.
[9]	LI Ren-jie, WEI Hui-xiang, LI Cheng, XU Zhuang, WANG Wen-shan, WANG Liang, BI Feng. Structure design and analysis of feeder in CFETR toroidal field coil [J]. Nuclear Fusion and Plasma Physics, 2021, 41(4): 623-627.
[10]	WEI Hai-hong, LI Peng-yuan, ZHANG Teng, XU Dan, XU Wan-yun, SUN Zhen-chao, LUO rong-rong . Optimization design and manufacture of cooling system for ITER PF6 magnet support [J]. Nuclear Fusion and Plasma Physics, 2021, 41(4): 635-641.
[11]	TAO La-bao1, 2, YANG Qing-xi1, XU Hao1, LI Ning1,CHEN Jian1, LU Kun1, ZHOU Cai-pin3. Demonstration and calculation of rupture discs in vacuum vessel pressure suppression system of CFETR [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2020, 40(2): 162-167.
[12]	WU Jing, WANG Ping-huai, CHEN Ji-ming, YUAN Tao,ZHU Xiao-bo, LI Qian, GAO Hui, KANG Wei-shan. Preliminary design of pipe joint assembly type ITER enhanced heat load first wall [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2020, 40(1): 65-71.
[13]	FAN Xiao-song, WU Jie-feng, LIU Zhi-hong, GU Yong-qi. Analysis for welding of 1/32 vacuum vessel sector of future fusion engineering test reactor [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2019, 39(1): 55-61.
[14]	ZHANG Jian-zhong, CHEN Ke, WANG Yan. Structural design and strength analysis of supporting rib in ITER vacuum vessel [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2017, 37(4): 441-445.
[15]	XIA Zhi-wei, LI Wei, LI Bo. Estimation of magnetic force exerted on shield in gradient DC magnetic field [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2017, 37(1): 48-51.