2017•IEEE Transactions on Applied SuperconductivityOpen access

Manufacturing of Nb3Sn Sample Conductor for CFETR Central Solenoid Model Coil

Jinggang Qin, Yu Wu, Bing-Lun Xiang, Chao Dai, Zhe-Hua Mao, Huan Jin, Guo-Jun Liao, Fang Liu, Tianjun Xue, Zhou-Rong Wei, A. Devred, Arend Nijhuis, Chao Zhou

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Abstract

China fusion engineering test reactor (CFETR) is a new tokamak device, whose magnet system includes the toroidal field, central solenoid (CS), and poloidal field coils. In order to develop the manufacturing process for the full-size CS coil, the CS model coil (CSMC) project was launched first. The cable-in-conduit conductor used for CFETR CSMC refers to ITER CS conductor with the same short twist pitch cable pattern. They have the similar layout. In order to qualify the manufacturing process and performance of conductor, two short sample conductors with two different jacket materials (316LN and high-Mn steel) were manufactured. The conductors were tested at Swiss Plasma Center successfully. In future, the CSMC will be tested at the Institute of Plasma Physics, CAS (ASIPP). In this paper, the manufacturing processes for conductor are described in detail. The strand damage analysis and conductor performance were also discussed.

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What this paper is about

China fusion engineering test reactor (CFETR) is a new tokamak device, whose magnet system includes the toroidal field, central solenoid (CS), and poloidal field coils. In order to develop the manufacturing process for the full-size CS coil, the CS model coil (CSMC) project was launched first. The cable-in-conduit conductor used for CFETR CSMC refers to ITER CS conductor with the same short twist pitch cable pattern. They have the similar layout. In order to qualify the manufacturing process and performance of conductor, two short sample conductors with two different jacket materials (316LN and high-Mn steel) were manufactured. The conductors were tested at Swiss Plasma Center successfully. In future, the CSMC will be tested at the Institute of Plasma Physics, CAS (ASIPP). In this paper, the manufacturing processes for conductor are described in detail. The strand damage analysis and conductor performance were also discussed.

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Available abstract

China fusion engineering test reactor (CFETR) is a new tokamak device, whose magnet system includes the toroidal field, central solenoid (CS), and poloidal field coils. In order to develop the manufacturing process for the full-size CS coil, the CS model coil (CSMC) project was launched first. The cable-in-conduit conductor used for CFETR CSMC refers to ITER CS conductor with the same short twist pitch cable pattern. They have the similar layout. In order to qualify the manufacturing process and performance of conductor, two short sample conductors with two different jacket materials (316LN and high-Mn steel) were manufactured. The conductors were tested at Swiss Plasma Center successfully. In future, the CSMC will be tested at the Institute of Plasma Physics, CAS (ASIPP). In this paper, the manufacturing processes for conductor are described in detail. The strand damage analysis and conductor performance were also discussed.

Key concepts: Solenoid, Conductor, Niobium-tin, Electromagnetic coil, Electrical conductor, Superconducting magnet, Tokamak, Materials science

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