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Abstract

The ITER Toroidal Field Model Coil 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 60s ramp heating run tends to overestimate the cable performance compared to the strand performance.

Additional information

Authors: MARINUCCI C, Association EURATOM-Confédération Suisse, Centre de Recherches en Physique des Plasmas, École Polytechnique Fédérale de Lausanne (CH);BRUZZONE P, Association EURATOM-Confédération Suisse, Centre de Recherches en Physique des Plasmas, École Polytechnique Fédérale de Lausanne (CH);BOTTURA P, CERN, Division LHC-MTA, Geneva (CH)
Bibliographic Reference: An oral report given at: 22nd Symposium on Fusion Technology (SOFT) Organised by: Association Euratom-Tekes Held at: Helsinki (FI), 9-13 September 2002
Availability: This paper is contained in report LRP 733/02, available free of charge from: École Polytechnique Fédérale de Lausanne (EPFL), Ecublens, CH-1015 Lausanne Fax +41-21-6934747
Record Number: 200215666 / Last updated on: 2002-12-16
Category: PUBLICATION
Original language: en
Available languages: en