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(ITERP1/23) The ITER Toroidal Field Model Coil (TFMC) Development Programme

   
E. Salpietro ¹, R. Maix ¹, G. Bevilacqua ¹, N. Mitchell ², B. Turck ³, A. Ulbricht ⁴, M. Spadoni ^5
 
1 The NET Team, Boltzmannstr.2, D-85748 Garching, Germany
² ITER Naka JCT, Naka, 311-0193 Japan
³ Association Euratom-CEA/Cadarache, F-13108 Saint Paul lez Durance, France
⁴ Association Euratom-FZK, Forschungszentrum, D-76021 Karlsruhe, Germany
⁵ Association Euratom-ENEA, I-00044 Frascati, Italy

Abstract
The TF coils for ITER  will use the concept of a circular thin walled $\rm Nb_3Sn$ cable in conduit superconductor completely enclosed in an insulated groove in steel plates to form the coil pancakes. These are then stacked together to form the winding pack and supported by a AISI 316LN stainless steel case. The concept is being demonstrated by the fabrication of a racetrack shaped model coil (TFMC) which is designed to operate mecanically, electrically and hydraulically in conditions representative for the ITER TF coils. For this purpose the TFMC will be assembled in the TOSKA facility at FZK Karlsruhe, together with the EURATOM LCT  coil which provides an external field. The objectives of the TFMC are as follows:

• To develop and verify the full scale TF coil manufacturing techniques;
• to establish realistic manufacturing tolerances;
• to bench-mark methods for the ITER TF coil acceptance;
• to gain information on the coil's behaviour, operating margins and in-service monitoring techniques.

The TFMC is actually in an advanced state of manufacture. Thus a large part of the first three objectives is reached. The TFMC will be delivered to FZK in summer 1999 to be prepared there for testing in TOSKA . Connected wit the ITER TFMC two other progammes are running in parallel, namely:

• a joint development programme which foresees the production and test of three full size joint samples;
• the fabrication of full size sections of the ITER TF coil case and radial plate.

       

Read the full paper in PDF format.