Title :
Resistances of electrical joints in the TF model coil of ITER: comparisons of first test results with samples results
Author :
Ciazynski, D. ; Ricci, M. ; Duchateau, J.L. ; Marchese, V. ; Ulbricht, A. ; Wuechner, F. ; Zahn, G. ; Fillunger, H. ; Maix, R.
fDate :
3/1/2002 12:00:00 AM
Abstract :
The test of the Toroidal Field (TF) Model Coil of the International Thermonuclear Experimental Reactor (ITER) has been the opportunity to measure the DC resistances of all the joints of a real coil and to compare them to values previously measured on prototype full-size joint samples. This paper describes and discusses the different methods used for measuring all the joint resistances, and gives the results of joint resistance measurements (1-2 nΩ range) as function of the coil current up to the maximum value of 80 kA. Comparisons with resistances measured on prototype joints in relevant field/current conditions are presented and discussed.
Keywords :
Tokamak devices; electric resistance measurement; fusion reactor design; plasma toroidal confinement; plasma transport processes; superconducting coils; 0 to 80 kA; 1 to 2 nohm; ITER; International Thermonuclear Experimental Reactor; coil current; electrical joint resistances; toroidal field model coil; Coils; Conductors; Current measurement; Electric variables measurement; Electrical resistance measurement; Magnetic field measurement; Power cables; Prototypes; Superconducting cables; Testing;
Journal_Title :
Applied Superconductivity, IEEE Transactions on
DOI :
10.1109/TASC.2002.1018462