The development of ITER TF model coil heat treatment conditions

Author

Abdioukhanov, I. ; Beliakov, V. ; Cheverev, N. ; Dergunova, E. ; Filatov, O. ; Kouznetsov, S. ; Mareev, K. ; Pantsyrnyi, V. ; Rodin, I. ; Silaev, A. ; Sinitsyn, I. ; Shikov, A. ; Sytnikov, V. ; Vorobieva, A.

Author_Institution

SSC RF A.A. Bochvar All Russia Res. Inst. of Inorg. Mater., Moscow, Russia

Volume

12

Issue

1

fYear

2002

fDate

3/1/2002 12:00:00 AM

Firstpage

1105

Lastpage

1108

Abstract

The Russian Toroidal Field (TF) Coil-Insert for a model coil of the Central Solenoid (CS) with Nb₃Sn cable-in-conduit conductor (CICC) in the Ti conduit was created in frame of the International Thermonuclear Experimental Reactor (ITER) Project. The schedule of Nb₃Sn CICC heat treatment was developed and optimized during preliminary study. Heat treatments of Nb₃Sn CICC sample and "dummy" CICC (the "dummy" CICC spiral was identical to the Nb₃Sn one with one exception: the copper wires with Cr-covering of the same size were used instead of the Nb₃Sn strands) were performed. The results of the study of the CICC elements, including jacket material, before and after heat treatment are described. The heat treatment conditions were developed and the heat treatment regulations were corrected on base of the results obtained.

Keywords

fusion reactor design; fusion reactor materials; heat treatment; niobium alloys; superconducting coils; superconducting magnets; tin alloys; type II superconductors; Central Solenoid; ITER TF model coil heat treatment conditions; International Thermonuclear Experimental Reactor; Nb₃Sn; Russian Toroidal Field; cable-in-conduit conductor; fusion reactors; heat treatment; superconducting magnets; Coils; Conductors; Copper; Heat treatment; Inductors; Niobium; Solenoids; Spirals; Tin; Wires;

fLanguage

English

Journal_Title

Applied Superconductivity, IEEE Transactions on

Publisher

ieee

ISSN

1051-8223

Type

jour

DOI

10.1109/TASC.2002.1018594

Filename

1018594