Stability analysis on Nb3Sn sample conductor of CFETR central solenoid model coil

Mei, Chao; Wu, Yu; Li, Jiangang; Qin, Jinggang; Liu, Fang; Liu, Huajun; Shi, Yi; Zhou, Chao; Liu, Sheng

doi:10.1016/j.fusengdes.2018.05.079

Cited by 9 publications

(1 citation statement)

References 19 publications

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“…The slope value b reflects the impact of transverse EM load to the conductor performance. The value b of CSJA-3 and CFETR CSMC conductor sample are 1.54 and 1.42 respectively [8,24], which indicates that the performance of this conductor sample, made of high-J c Nb 3 Sn strand, is more sensitive to transverse EM load than that of CSJA-3 and CFETR CSMC conductor, which are made of ITER-grade Nb 3 Sn strand. But it also depends on the internal structure of the high-J c Nb 3 Sn strand, i.e.…”

Section: T Cs Evolutionmentioning

confidence: 91%

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J _c Nb₃Sn strand for fusion reactor

Dai

Wang

et al. 2021

Nucl. Fusion

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The Comprehensive Research Facility for Fusion Technology (CRAFT) project has been launched in 2019, for developing the essential engineering technologies for Chinese Fusion Engineering Testing Reactor (CFETR). Within this project, a full-size toroidal field (TF) coil will be built as the prototype coil for CFETR. Based on design of CFETR magnet system, the TF coil will operate at 95.6 kA in a peak field of 14.5 T. The high-J c Nb3Sn strand is taken into consideration due to the critical current density of ITER-grade Nb3Sn is too low at 14.5 T. Considering that it will be the first time to apply the high-J c Nb3Sn strand in the large-scale cable-in-conduit conductor (CICC) for fusion magnet, a conductor sample made of high-J c Nb3Sn strand with short twist pitch (STP) cable pattern was manufactured in ASIPP and tested in SULTAN facility, to investigate the feasibility. The test campaign focuses on the impact of cyclic electromagnetic (EM) loading and warm-up cool-down (WUCD) to the performance of the conductor, the strain distribution of the conductor before and after EM cycles was measured by inductive method to make a deeper insight of the conductor performance evolution. AC losses tests have also been carried out, providing relevant information for further coil design.

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Section: T Cs Evolutionmentioning

confidence: 91%

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J _c Nb₃Sn strand for fusion reactor

Dai

Wang

et al. 2021

Nucl. Fusion

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Preliminary Design of CFETR TF Prototype Coil

Wang

Shen

et al. 2021

J Fusion Energ

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Conductor design and performance analysis for CFETR magnet

Hao

Hussain²,

Dai³

et al. 2022

Fusion Engineering and Design

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Stability analysis on Nb3Sn sample conductor of CFETR central solenoid model coil

Cited by 9 publications

References 19 publications

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J _c Nb₃Sn strand for fusion reactor

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J _c Nb₃Sn strand for fusion reactor

Preliminary Design of CFETR TF Prototype Coil

Conductor design and performance analysis for CFETR magnet

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Stability analysis on Nb3Sn sample conductor of CFETR central solenoid model coil

Cited by 9 publications

References 19 publications

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J c Nb3Sn strand for fusion reactor

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J c Nb3Sn strand for fusion reactor

Preliminary Design of CFETR TF Prototype Coil

Conductor design and performance analysis for CFETR magnet

Contact Info

Product

Resources

About

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J _c Nb₃Sn strand for fusion reactor

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J _c Nb₃Sn strand for fusion reactor