Development of Evaluation Procedure for Superconductivity of CIC Conductor for Fusion Reactor
Author:
Affiliation:
1. Faculty of Science and Engineering, Waseda University
2. Japan Atom Energy Agency
Publisher
Cryogenic Association of Japan
Link
https://www.jstage.jst.go.jp/article/jcsj/51/3/51_71/_pdf
Reference14 articles.
1. 1) C. Sborchia1, et al.: “The ITER magnet systems: progress on construction”, IAEA nuclear fusion 54 (2014) 013006
2. 2) P. Bruzzone, et al.: “Qualification tests for ITER TF conductors in SULTAN”, Fusion Eng. 84(2009) 205-209
3. 3) N. Mitchell: “Summary, assessment and implications of the ITER model coil test results”, Fusion Eng. 66-68 (2003) 971-973
4. 4) N. Mitchell: “Assessment of conductor degradation in the ITER CS insert coil and implications for the ITER conductor”, Supercond. Sci. Technol. 20 (2007) 25-34
5. 5) N. Koizumi, et al.: “A new model to simulate critical current degradation of a large CICC by taking into account strand bending”, IEEE Trans. Appl. Supercond. 16 (2006) 831-834
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