Abstract
The Tokamak HT-7U project has been funded as a Chinese national project since 1998. The machine is designed by the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP). The main object of the project is to build a nuclear fusion experimental device with divertor configuration. It is a fully superconducting device, consisting of superconducting toroidal field (TF) coils and super-conducting poloidal field (PF) coils. This paper describes the design of TF conductors, including pool boiling cooled conductor (PBCC) and cable-in-conduit conductor (CICC). The CICC design is based on UNK NbTi wires made in Russia, cooled with supercritical helium. The other (PBCC) is based on SSC cables. Both versions can satisfy the design requirements. The modification of the conductor design including their main parameters, the configuration, and analysis of stability for both conductors are given.
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