抄録
In the design of the International Thermonuclear Experimental Reactor (ITER), a forced flow cooled, Cable-In-Conduit Conductor (CICC) is selected for its magnet system because of its superior performance in withstanding voltage (>10kV) and, more importantly, its mechanical stiffness against large electromagnetic forces. The CICC consists of about 1,000 superconducting strands enclosed in a steel jacket, and due to this configuration, the CICC exhibits a characteristic electromagnetic phenomena which can be a cause of the instability of a conductor. Extensive studies were performed, especially on ac losses, stability, and current imbalance among the strands in order to understand the phenomena and to provide a design basis for CICC to be used in large superconducting magnets. This paper describes the work on developing the CICC including analytic studies regarding the realization of fusion magnets.
