Rebuilding of the HT-7 TF coil current leads

Author

Jie, Y. ; Chen, X.Q. ; Gao, D.M. ; Wu, J.F.

Author_Institution

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

Volume

2

fYear

1997

fDate

6-10 Oct 1997

Firstpage

649

Abstract

The paper presents technical schemes and technological methods on the reconstruction of HT-7 current leads unit to satisfy physics requirements. At first, structure characteristics and design parameters on the current leads are described. The comparison between the former leads and the new ones is made. Secondly, fabricating steps necessary to reconstruct the leads and a series of technological methods to solve the techniques are reported. Then, based on the stress analysis and mechanical properties at low temperature on some kinds of materials used in LHe system, the stress weak links and improvement methods are discussed. Finally, the vacuum test and status of LHe system including the current leads after rebuilding are given

Keywords

Tokamak devices; fusion reactor design; superconducting magnets; HT-7 toroidal field coil current leads; LHe system; mechanical properties; physics requirements; stress analysis; stress weak links; vacuum test; Copper; Current measurement; Fluid flow measurement; Manufacturing; Physics; Plasma temperature; Pressure measurement; Spirals; Stress; Tokamaks;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1997. 17th IEEE/NPSS Symposium

Conference_Location

San Diego, CA

Print_ISBN

0-7803-4226-7

Type

conf

DOI

10.1109/FUSION.1997.687710

Filename

687710