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

Abstract

<para xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink"> 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 <formula formulatype="inline"><tex>${\rm Nb}_{3}{\rm Sn}$</tex></formula> 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 <formula formulatype="inline"><tex>$(T_{cs})$</tex></formula> margins for these coils were performed by the one-dimensional fluid analysis code with transient heat loads. The <formula formulatype="inline"><tex>$T_{cs}$</tex></formula> margins of these coils are <formula formulatype="inline"><tex>$&gt;$</tex></formula>1 K for the plasma standard and disruption scenarios. The minimum <formula formulatype="inline"> <tex>$T_{cs}$</tex></formula> 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 <formula formulatype="inline"><tex>$T_{cs}$</tex> </formula> margin of the coil by <formula formulatype="inline"><tex>$&gt;$</tex> </formula>1 K. A coupling time constant of <formula formulatype="inline"> <tex>$≪$</tex></formula>100 ms, Ni plating, and a central spiral are required for NbTi conductor. </para>