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

Author

Weng, P.D. ; Chen, Z.M. ; Bi, Y.F. ; Li, B.Z. ; Wu, S.T. ; Wu, W.Y.

Author_Institution

Inst. of Plasma Phys., Acad. Sinica, Anhui, China

Volume

10

Issue

1

fYear

2000

fDate

3/1/2000 12:00:00 AM

Firstpage

1078

Lastpage

1081

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.

Keywords

Tokamak devices; fusion reactor design; fusion reactor divertors; superconducting coils; superconducting magnets; HT-7U TF magnet; NbTi; NbTi wire; SSC cable; Tokamak machine; cable-in-conduit conductor; conductor design; divertor; nuclear fusion device; pool boiling cooled conductor; stability analysis; superconducting poloidal field coil; superconducting toroidal field coil; Conductors; Fusion reactors; Magnets; Nuclear and plasma sciences; Physics; Plasma devices; Superconducting cables; Superconducting coils; Superconducting devices; Tokamaks;

fLanguage

English

Journal_Title

Applied Superconductivity, IEEE Transactions on

Publisher

ieee

ISSN

1051-8223

Type

jour

DOI

10.1109/77.828419

Filename

828419