IEEE Transactions on Applied Superconductivity · 2014 · 47 citations · 15 references
Natural SciencesNuclear EngineeringPhysicsCondensed Matter PhysicsFusion EngineeringPlasma PhysicsFusion PlasmasFusion Reactor MaterialsHigh-temperature PlasmasMagnetic Confinement FusionNuclear FusionSuperconducting MaterialsCritical Current DensityCritical Current PerformanceCurrent DensityExcitationFusion Reactor PhysicsHigh-temperature SuperconductivityMagnetic Field IntensityTokamak Plasmas
Based on the successful plasma experiments in the Large Helical Device (LHD), design activities of the LHD-type helical fusion reactor FFHR-d1 are progressing at National Institute for Fusion Science (NIFS). A 100 kA current capacity is required for the winding conductor under the maximum magnetic field of ~12 T. The high-temperature superconductor (HTS) is a promising option for the helical coil conductor. For the development of such a HTS conductor suitable for the helical fusion reactor, we fabricated 30 kA-class HTS conductor samples, and the excitation tests were successfully carried out. We then fabricated and tested a 100-kA class HTS conductor. The conductor sample is a one-turn short-circuit coil with a race-track shape having a bridge-type mechanical lap joint. The transport current of the sample was induced by changing the external magnetic field, then the critical current of the sample was measured. A numerical analysis of the critical current is being performed by self-consistently solving the spatial distributions of the current density and magnetic field among the simply-stacked HTS tapes to verify the measured critical current of the samples. The critical current characteristics of a single HTS tape is evaluated by the percolation model in the precise analysis.
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Helical reactor design FFHR-d1 and c1 for steady-state DEMO
A. Sagara, H. Tamura, Teruya Tanaka et al. · Fusion Engineering and Design · 2014 · 125 citations
M. Inoue, T. Kiss, D. Mitsui et al. · IEEE Transactions on Applied Superconductivity · 2007 · 37 citations · Full text
Natural Sciences, Materials Engineering, Materials Science +15
High-Temperature Superconducting Coil Option for the LHD-Type Fusion Energy Reactor FFHR
G. Bansal, N. Yanagi, T. Hemmi et al. · Plasma and Fusion Research · 2008 · 34 citations · Full text