Design and Analysis of a Superconducting Cable-in-Conduit Test Coil for Operation at 15 T and 40A/m(sup 2).

摘要

The International Thermonuclear Experimental Reactor (ITER) Design Team may use coil current densities as high as 40 A(center dot)mm(sup -2) and peak magnetic fields of 12--15 T to size superconducting coils in a tokamak reactor design. To verify that these values are within the present superconducting magnet technology state-of-the-art, we are building a Proof of Principles (PoP) test coil. The PoP will be inserted into the bore of an existing High-Field Test Facility Solenoid magnet at LLNL. The PoP insert will be a solenoid coil with approximate dimensions of: 1-m, outside diameter; 0.5-m, inside diameter; about 0.5-m, height. The overall coil fabrication will use the insulate-wind-react-impregnate method. The quartz-cloth-tape insulation material will be wrapped onto the conductor as part of the coil-winding process. The coil will be layer-wound using cable-in-conduit conductor (CICC) with all splices and connections located at the coil ends. The Ti-modified, internal-tin process, MF-Nb(sub 3)Sn technique will be used to produce the superconducting composite wire for the CICC. After reaction, the epoxy component of the insulation system will be added by vacuum impregnation. We describe details of the coil design and analysis and relate them to needs within the engineering data base supporting the design of magnet systems for ITER. 5 refs., 8 figs., 1 tab.