Title :
Analysis and interpretation of Tcs tests of the ITER toroidal field conductor insert
Author :
Marinucci, C. ; Bottura, L. ; Bruzzone, P. ; Mitchell, N. ; Stepanov, B. ; Wesche, R.
Author_Institution :
CRPP Fusion Technol., Villigen PSI, Switzerland
fDate :
6/1/2004 12:00:00 AM
Abstract :
The toroidal field conductor insert (TFCI) coil was tested at 46 kA in the 13 T background magnetic field generated by the central solenoid model coil. The single layer TFCI coil uses a Nb3Sn cable-in-conduit conductor in a titanium jacket. The object of this work is to verify the data self-consistency, and to apply a thermal, hydraulic and electrical simulation to derive the strand performance in the cable. We present the results of the analysis in support of the interpretation of a subset of current sharing temperature measurements. After estimation of the n-value in the voltage-current equation, we perform the simulations using the total longitudinal strain as the only fitting parameter; the resulting value is much larger than the value expected from simple thermal contraction considerations.
Keywords :
Tokamak devices; computational electromagnetics; deformation; fusion reactor design; niobium alloys; simulation; superconducting magnets; thermal analysis; tin alloys; titanium; type II superconductors; 13 T; 46 kA; ITER; Nb3Sn; Tcs test; TFCI coil; Ti; cable-in-conduit conductor; central solenoid model coil; current sharing temperature measurements; data self-consistency; electrical simulation; hydraulic simulation; longitudinal strain; magnetic field generation; n-value extimation; strand performance; thermal contraction; thermal simulation; titanium jacket; toroidal field conductor insert; voltage-current equation; Cable shielding; Coils; Conductors; Magnetic analysis; Niobium; Solenoids; Testing; Tin; Titanium; Toroidal magnetic fields; Cable-in-conduit; ITER; computational thermal-hydraulics; superconducting magnets;
Journal_Title :
Applied Superconductivity, IEEE Transactions on
DOI :
10.1109/TASC.2004.830685