Abstract
The ITER toroidal field model coil (TFMC) has been tested in the TOSKA facility of FzK. The racetrack coil, which uses a circular Nb3Sn cable-in-conduit conductor, is equipped with external resistive heaters for the evaluation of the current sharing temperature (Tcs). Since there are no sensors inside the coil, the only possibility to assess the coil temperature is to use the measured inlet temperature and to estimate the downstream propagation of the temperature profile. The analysis has shown that a quantitative assessment of Tcs from the test results of the 60 s ramp heating run tends to overestimate the cable performance compared with the strand performance.
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