The modifications of conductor design for HT-7U TF magnets

The Tokamak HT-7U project has been funded as a Chinese national project sin ce 1998. The machine is designed by the Institute of Plasma Physics, Chines e Academy of Sciences (ASIPP). The main object of the project is to build a nuclear fusion experimental device with divertor configuration. It is a fu lly 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 co oled conductor (PBCC) and cable-in-conduit conductor (CICC). The CICC desig n is based on UNK NbTi wires made in Russia, cooled with supercritical heli um. The other (PBCC) is based on SSC cables. Both versions can satisfy the design requirements. The modification of the conductor design including the ir main parameters, the configuration, and analysis of stability for both c onductors are given.