Development of a forced-cooled superconducting coil for fusion applications
説明
A test coil was wound from a NbTi cable-in-conduit type conductor with 54 strands, and the total conductor length was 36 m. It was force-cooled with supercritical helium. The critical current of the test coil was 3.5 kA at 7 T. The test coil was installed in a backup coil which generated the magnetic field up to 7 T. The experimental results from the propagation velocity of the normal zone and the pressure rise when the force-cooled superconducting coil is quenched are described. The results of an analysis of the stability margin of the coil using computer simulation are reported. >
収録刊行物
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- IEEE Thirteenth Symposium on Fusion Engineering
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IEEE Thirteenth Symposium on Fusion Engineering 1177-1180, 2003-01-13
IEEE