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Preparation of the ITER poloidal field conductor insert (PFCI) test
Zanino, R.,Egorov, S.,Kim, K.,Martovetsky, N.,Nunoya, Y.,Okuno, K.,Salpietro, E.,Sborchia, C.,Takahashi, Y.,Weng, P.,Bagnasco, M.,Richard, L.S.,Polak, M.,Formisano, A.,Zapretilina, E.,Shikov, A.,Veder IEEE 2005 IEEE transactions on applied superconductivity Vol.15 No.2
The Poloidal Field Conductor Insert (PFCI) of the International Thermonuclear Experimental Reactor (ITER) has been designed in the EU and is being manufactured at Tesla Engineering, UK, in the frame of a Task Agreement with the ITER International Team. Completion of the PFCI is expected at the beginning of 2005. Then, the coil shall be shipped to JAERI Naka, Japan, and inserted into the bore of the ITER Central Solenoid Model Coil, where it should be tested in 2005 to 2006. The PFCI consists of a NbTi dual-channel conductor, almost identical to the ITER PF1 and PF6 design, ∼45 m long, with a 50 mm thick square stainless steel jacket, wound in a single-layer solenoid. It should carry up to 50 kA in a field of ∼6 T, and it will be cooled by supercritical He at ∼4.5 K and ∼0.6 MPa. An intermediate joint, representative of the ITER PF joints and located at relatively high field, will be an important new item in the test configuration with respect to the previous ITER Insert Coils. The PFCI will be fully instrumented with inductive and resistive heaters, as well as with voltage taps, Hall probes, pick-up coils, temperature sensors, pressure gauges, strain and displacement sensors. The test program will be aimed at DC and pulsed performance assessment of conductor and intermediate joint, AC loss measurement, stability and quench propagation, thermal-hydraulic characterization. Here we give an overview of the preparatory work toward the test, including a review of the coil manufacturing and of the available instrumentation, a discussion of the most likely test program items, and a presentation of the supporting modeling and characterization work performed so far.
Results of a New Generation of ITER TF Conductor Samples in SULTAN
Bruzzone, P.,Stepanov, B.,Wesche, R.,Salpietro, E.,Vostner, A.,Okuno, K.,Isono, T.,Takahashi, Y.,Hyoung Chan Kim,Keeman Kim,Shikov, A.K.,Sytnikov, V.E. IEEE 2008 IEEE transactions on applied superconductivity Vol.18 No.2
<P>A new generation of ITER TF conductor samples has been assembled and tested in SULTAN in 2007 following a common procedure agreed among the ITER parties. The test results of six SULTAN samples, made of twelve conductor sections manufactured in Europe, Japan, Korea and Russia, are reported here. The conductor layout reflects the ITER TF conductor design, with minor differences for the Nb<SUB>3</SUB>Sn strand characteristics, void fraction and twist pitch. The object of the test is a straight comparison with the ITER requirement of 5.7 K current sharing temperature at 68 kA current and 11.3 T field. A broad range of behavior is observed.</P>