Design of the prototype conductors for the Fusion Experimental Reactor

Author

Yoshida, K. ; Nishi, W.F. ; Takahashi, Y. ; Tsuji, H. ; Koizumi, K. ; Okuno, K. ; Ando, T.

Author_Institution

JAERI, Ibaraki, Japan

Volume

25

Issue

2

fYear

1989

fDate

3/1/1989 12:00:00 AM

Firstpage

1488

Lastpage

1491

Abstract

The prototype conductors of the toroidal coil for the Fusion Experimental Reactor have been investigated. Specifications of the conductor are as follows: forced flow cooling; rated current of 30 kA at 12 T and 4.2 K; margin of critical current of 2; current density in winding of 30-40 A/mm²; inlet helium at 4.2 K and 4-10 bar; and minimum bending radius of 1.5 m. Three types of conductors were considered as candidates: a test module coil of FF type (hollow cooling type using test module coil Nb₃Sn conductor techniques); preformed armor type; and advanced disk type. Detailed design parameters and analysis results are given for the three candidate conductors

Keywords

conductors (electric); fusion reactor theory and design; niobium alloys; superconducting magnets; tin alloys; 30 kA; 4 to 10 bar; 4.2 K; Fusion Experimental Reactor; He; Nb₃Sn; critical current; prototype conductors; superconducting magnet; test module coil; toroidal coil; Coils; Conductors; Cooling; Critical current; Current density; Fusion reactor design; Helium; Inductors; Prototypes; Testing;

fLanguage

English

Journal_Title

Magnetics, IEEE Transactions on

Publisher

ieee

ISSN

0018-9464

Type

jour

DOI

10.1109/20.92577

Filename

92577