Fabrication of the KSTAR superconducting CICC

Author

Lim, B.S. ; Lee, S.I. ; Kim, K.M. ; Choi, J.Y.

Author_Institution

Samsung Adv. Inst. of Technol., Taejon, South Korea

Volume

12

Issue

1

fYear

2002

fDate

3/1/2002 12:00:00 AM

Firstpage

591

Lastpage

594

Abstract

A superconducting cable-in-conduit conductor (CICC) is adopted for the Korea Superconducting Tokamak Advanced Research (KSTAR) superconducting magnet system which consists of 16 TF coils and 14 PF coils. The KSTAR Magnet system uses two different types of CICCs-Nb₃Sn cable with Incoloy 908 conduit and NbTi cable with 316LN stainless-steel conduit. A continuous CICC jacketing system is developed for the KSTAR CICC fabrication and the jacketing system uses the tube-mill process, which consists of forming, welding, sizing and squaring procedures. The design specification of CICCs and the fabrication process is described. The welding of the Incoloy 908 strip joint is also discussed. The fabrication results including the geometrical specification and the void fraction will be discussed.

Keywords

Tokamak devices; cable sheathing; chromium alloys; electric conduits; forming processes; fusion reactor design; iron alloys; nickel alloys; niobium compounds; plasma toroidal confinement; stainless steel; superconducting magnets; welding; Incoloy 908 strip joint; KSTAR superconducting CICC; Korea Superconducting Tokamak Advanced Research superconducting magnet system; Nb₃Sn; NbTi; cable; coils; forming; geometrical specification; jacketing system; sizing; squaring; stainless-steel conduit; superconducting cable-in-conduit conductor; tube-mill process; void fraction; welding; Cable shielding; Conductors; Fabrication; Niobium compounds; Superconducting cables; Superconducting coils; Superconducting magnets; Tin; Tokamaks; Welding;

fLanguage

English

Journal_Title

Applied Superconductivity, IEEE Transactions on

Publisher

ieee

ISSN

1051-8223

Type

jour

DOI

10.1109/TASC.2002.1018473

Filename

1018473