Abstract
The Russian Toroidal Field (TF) Coil-Insert for a model coil of the Central Solenoid (CS) with Nb/sub 3/Sn cable-in-conduit conductor (CICC) in the Ti conduit was created in frame of the International Thermonuclear Experimental Reactor (ITER) Project. The schedule of Nb/sub 3/Sn CICC heat treatment was developed and optimized during preliminary study. Heat treatments of Nb/sub 3/Sn CICC sample and "dummy" CICC (the "dummy" CICC spiral was identical to the Nb/sub 3/Sn one with one exception: the copper wires with Cr-covering of the same size were used instead of the Nb/sub 3/Sn 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.
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