New design of cable-in-conduit conductor for application in future fusion reactors

Jinggang Qin*, Yu Wu, Jiangang Li, Fang Liu, Chao Dai, Yi Shi, Huajun Liu, Zhehua Mao, Arend Nijhuis, Chao Zhou, Kostyantyn Yagotyntsev, Ruben Lubkemann, Valiyaparambil Abdulsalam Anvar, Arnaud Devred

*Corresponding author for this work

Research output: Contribution to journalArticleAcademicpeer-review

21 Citations (Scopus)
1 Downloads (Pure)


The China Fusion Engineering Test Reactor (CFETR) is a new tokamak device whose magnet system includes toroidal field, central solenoid (CS) and poloidal field coils. The main goal is to build a fusion engineering tokamak reactor with about 1 GW fusion power and self-sufficiency by blanket. In order to reach this high performance, the magnet field target is 15 T. However, the huge electromagnetic load caused by high field and current is a threat for conductor degradation under cycling. The conductor with a short-twist-pitch (STP) design has large stiffness, which enables a significant performance improvement in view of load and thermal cycling. But the conductor with STP design has a remarkable disadvantage: it can easily cause severe strand indentation during cabling. The indentation can reduce the strand performance, especially under high load cycling. In order to overcome this disadvantage, a new design is proposed. The main characteristic of this new design is an updated layout in the triplet. The triplet is made of two Nb3Sn strands and one soft copper strand. The twist pitch of the two Nb3Sn strands is large and cabled first. The copper strand is then wound around the two superconducting strands (CWS) with a shorter twist pitch. The following cable stages layout and twist pitches are similar to the ITER CS conductor with STP design. One short conductor sample with a similar scale to the ITER CS was manufactured and tested with the Twente Cable Press to investigate the mechanical properties, AC loss and internal inspection by destructive examination. The results are compared to the STP conductor (ITER CS and CFETR CSMC) tests. The results show that the new conductor design has similar stiffness, but much lower strand indentation than the STP design. The new design shows potential for application in future fusion reactors.

Original languageEnglish
Article number115012
Number of pages11
JournalSuperconductor science and technology
Issue number11
Publication statusPublished - 17 Oct 2017


  • Cable-in-conduit conductors
  • copper wound superconducting strand
  • magnetic cycling loading
  • nuclear fusion


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