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Conductor Design of CS and EF Coils for JT-60SA

2008; IEEE Council on Superconductivity; Volume: 18; Issue: 2 Linguagem: Inglês

10.1109/tasc.2008.920536

1558-2515

K. Kizu, Katsuhiko Tsuchiya, K. Yoshida, M. Edaya, T. Ichige, H. Tamai, M. Matsukawa, A. della Corte, A. Di Zenobio, L. Muzzi, S. Turtù, J.L. Duchateau, L. Zani,

Fusion materials and technologies

The conductor for central solenoid (CS) and equilibrium field (EF) coils of JT-60 Super Advanced (JT-60SA) were designed. The conductor for CS is ${\rm Nb}_{3}{\rm Sn}$ Cable-In-Conduit (CIC) conductor with JK2LB jacket. EF coil conductors are NbTi CIC conductor with SS316LN jacket. The field change rate (3.9 T/s), faster than ITER generates the large AC loss in conductor. The analyses of current sharing temperature $(T_{cs})$ margins for these coils were performed by the one-dimensional fluid analysis code with transient heat loads. The $T_{cs}$ margins of these coils are $>$ 1 K for the plasma standard and disruption scenarios. The minimum $T_{cs}$ margin of CS conductor is 1.2 K at plasma break down (BD). The margin is increased by decreasing the rate of initial magnetization. It is found that the disruption mainly impacts the outer low field EF coil. The disruption decreases the $T_{cs}$ margin of the coil by $>$ 1 K. A coupling time constant of $≪$ 100 ms, Ni plating, and a central spiral are required for NbTi conductor.