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DC performance and AC loss of cable-in-conduit conductors for International Thermonuclear Experimental Reactor

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Abstract

A reliable prediction of AC loss is essential for the application of International Thermonuclear Experimental Reactor (ITER) cable-in-conduit conductors (CICCs); however, the calculation of AC loss of ITER CICCs is a cumbersome task due to the complicated geometry of the multistage cables and the extreme operating conditions in ITER. In this paper, we described the models developed for hysteresis and coupling loss calculation, which can be suitable for the construction of ITER magnetic system. Meanwhile, we compared the results of theoretical analysis with the SULTAN test result to evaluate the numerical model we used. In addition, we introduced the n-value and AC loss with transport current for CICCs based on the DC measurement results at SULTAN, which lays the foundation for the further study.

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Acknowledgments

The authors would like to thank A. Devred, A. Vostner and C. Y. Gung from ITER Organization and D.-X. Chen from Universitat Autonoma de Barcelona for helpful discussion. We are thankful to University of Twente crew for strand preparation work and testing and ASIPP and CRPP personnel for providing some pictures and test results of TFCN4 conductor.

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Authors and Affiliations

  1. School of Electrical Engineering, Beijing Jiaotong University, Beijing, 100044, China

    Wei Zhou & Jin Fang

  2. Department of Electrical and Computer Engineering, University of Victoria, Victoria, BC, V8W2Y2, Canada

    Xin-Yu Fang

  3. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, 230031, China

    Bo Liu

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  1. Wei Zhou
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  2. Xin-Yu Fang
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  3. Jin Fang
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  4. Bo Liu
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Corresponding author

Correspondence to Jin Fang.

Additional information

This study was supported in part by Ministry of Science and Technology of China under Grant 2014GB105001.

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Zhou, W., Fang, XY., Fang, J. et al. DC performance and AC loss of cable-in-conduit conductors for International Thermonuclear Experimental Reactor. NUCL SCI TECH 27, 74 (2016). https://doi.org/10.1007/s41365-016-0061-2

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  • DOI: https://doi.org/10.1007/s41365-016-0061-2

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