DocumentCode :
1496807
Title :
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
Link To Document :
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