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The conductor for central solenoid (CS) and equilibrium field (EF) coils of JT-60 Super Advanced (JT-60SA) were designed. The conductor for CS isNb₃ SnCable-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(Tcs)margins for these coils were performed by the one-dimensional fluid analysis code with transient heat loads. TheTcsmargins of these coils are$>$1 K for the plasma standard and disruption scenarios. The minimumTcsmargin of CS conductor is 1.2 K at plasma break down (BD). The margin is increased by decreasing the rate of initial magnetization. It is found that the disruption mainly impacts the outer low field EF coil. The disruption decreases theTcsmargin of the coil by$>$1 K. A coupling time constant of$≪$100 ms, Ni plating, and a central spiral are required for NbTi conductor.
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Kizu et al. (2008) studied this question.
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