Title :
Tcs tests and performance assessment of the ITER toroidal field model coil (phase II)
Author :
Zanino, R. ; Bagnasco, M. ; Dittrich, G. ; Fietz, W.H. ; Fillunger, H. ; Hampshire, D.P. ; Heller, R. ; Komarek, P. ; Langhans, O. ; Maix, R. ; Marchese, V. ; Martovetsky, N. ; Mitchell, N. ; Nijhuis, A. ; Raff, S. ; Ricci, M. ; Suesser, M. ; Salpietro, E
Author_Institution :
Dipt. di Energetica, Politecnico, Torino, Italy
fDate :
6/1/2004 12:00:00 AM
Abstract :
The tests of the toroidal field model coil (TFMC) were completed in 2002 in the TOSKA facility of Forschungszentrum Karlsruhe, Germany. Operation reached a combined 80 kA in the TFMC and 16 kA in the LCT coil, resulting in a peak electromechanical load very close to that expected in the full-size ITER TF coils (800 kN/m). Here we concentrate on the measurements of the current sharing temperature Tcs of the TFMC conductor, possibly the highlight of the whole test campaign. These tests were performed by increasing in steps the helium inlet temperature Tin in double pancake DP1, resulting in an increasing normal voltage V across the DP1.1 and DP1.2 conductors, and were repeated for several combinations of currents in the TFMC and in the LCT coil. The analysis of the V - Tin characteristic by means of the M&M code allows to self-consistently deriving an estimate of Tcs, as well as an indirect assessment of the "average" strain state in the conductor. The TFMC isolated strand has also been very recently characterized at different applied uniaxial strain, and preliminary results indicate a stronger reduction of carrying capacity compared to the extrapolation from Summers scaling used in the analysis so far. As a consequence, the performance of the TFMC conductor, as preliminarily re-evaluated here, appears more in line with the strand performance than in previous analysis, although a BI-dependent "degradation" is still present.
Keywords :
Tokamak devices; bending; critical currents; fusion reactor design; helium; niobium alloys; superconducting coils; superconducting magnets; temperature measurement; tin alloys; type II superconductors; 16 kA; 80 kA; DP1.1 conductors; DP1.2 conductors; ITER TF coils; LCT coil; M&M code; Nb3Sn; Summers scaling; Tcs measurement; Tcs test; TFMC isolated strand; cable-in-conduit; current sharing temperature; double pancake DP1; electromechanical load; helium inlet temperature Tin; nuclear fusion; performance assessment; strain state; toroidal field model coil; uniaxial strain; Capacitive sensors; Coils; Conductors; Current measurement; Helium; Performance evaluation; State estimation; Temperature; Testing; Voltage; $hbox Nb_; Cable in conduit; hboxSn$ ; nuclear fusion; toroidal field coil;
Journal_Title :
Applied Superconductivity, IEEE Transactions on
DOI :
10.1109/TASC.2004.830682