Experimental Thermal Behaviour of the Toroidal Field Model Coil : Application to ITER TF Transient Regimes
- Departement de Recherches sur la Fusion Controlee, Association Euratom-CEA, CEA/Cadarache, F-13108 Saint Paul-lez-Durance (France)
- Atominstitut der Oesterreichischen Universitaeten, A-1020 Vienna (Austria)
- Forschungszentrum Karlsruhe, Institute fuer Technische Physik, Postfach 3640, D-76021 Karlsruhe (Germany)
The ITER Toroidal Field (TF) magnet is made of 18 coils. The 7 winding-pack modules constituting their structure, contain each one double pancake Cable-In-Conduit-Conductor (CICC) inserted in a stainless steel radial plate. The winding pack is enclosed inside a thick stainless steel case. During a safety discharge of the TF system, eddy currents and associated heat generation are induced in the plates and in the case. Such fast discharges have been performed during Phase I and Phase II experiment of the Toroidal Field Model Coil (TFMC) tests to investigate heat generation and transfer. Simple models have been developed to predict the behaviour of the coil during these transients. These models have been validated by calorimetric measurements. These models can also be used to estimate the temperature increase of the TF Conductor during a plasma disruption and to investigate whether a quench can happen.
- OSTI ID:
- 20653182
- Journal Information:
- AIP Conference Proceedings, Vol. 710, Issue 1; Conference: CEC 2003: Cryogenic engineering and international cryogenic materials conference on advances in cryogenic engineering, Anchorage, AK (United States), 22-26 Sep 2003; Other Information: DOI: 10.1063/1.1774744; (c) 2004 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
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