Abstract
The ITER toroidal field model coil (TFMC) was designed, constructed and tested by the European Home Team in the frame of the ITER research and development program of the Engineering Design Activities (EDA). The project was performed under the leadership of European Fusion Development Activity / Close Support Unit (EFDA / CSU), Garching. The TFMC was tested in the test phase I as single coil in the TOSKA facility of the Forschungszentrum Karlsruhe. The test confirmed that engineering design principles and manufacturing procedures are sound and suitable for the ITER TF full size coils. The electromagnetic, thermohydraulic and mechanical operation parameters agree well with predictions. An electrical insulation problem was localised in the ground insulation but led to no restrictions on the test operation.
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