Performance tests on an ITER relevant CICC Nb/sub 3/Sn coil

Author

Balsamo, E. ; Cicchelli, O. ; Cuomo, M. ; dell Corte, A. ; Gislon, P. ; Pasotti, G. ; Ricci, M. ; Spadoni, M.

Author_Institution

Assoc. EURATOM ENEA sulla Fusione, Rome, Italy

Volume

10

Issue

1

fYear

2000

fDate

3/1/2000 12:00:00 AM

Firstpage

572

Lastpage

575

Abstract

The central solenoid (CS) of a fusion reactor is expected to be operated around 13 T, 5.8 K, at ramp rates of 0.5-1 T/s. The present state of the art of the superconductor technology allows the fulfillment of such requirements only by means of coils made of cable-in-conduit Nb/sub 3/Sn conductors (CICC). In the ENEA Frascati Laboratory, the construction of a CICC Nb/sub 3/Sn coil (1m o.d., 0.6 m bore) was completed in 1994. Its original destination was the high field DC test facility SULTAN. Since many characteristics of this coil make it representative of a CS, it was decided that it was higher priority to test it in transient field conditions. An ad-hoc facility was designed and set up in the ENEA Frascati Laboratory.

Keywords

fusion reactor design; fusion reactor materials; niobium alloys; superconducting coils; superconducting magnets; tin alloys; type II superconductors; 0.6 m; 1 m; 13 T; 5.8 K; ENEA Frascati Laboratory; ITER relevant CICC coil; Nb/sub 3/Sn; cable-in-conduit conductors; central solenoid; fusion reactors; performance tests; superconducting coils; transient field conditions; Boring; Conductors; Fusion reactors; Laboratories; Niobium; Solenoids; Superconducting cables; Superconducting coils; Testing; Tin;

fLanguage

English

Journal_Title

Applied Superconductivity, IEEE Transactions on

Publisher

ieee

ISSN

1051-8223

Type

jour

DOI

10.1109/77.828299

Filename

828299