IEEE Transactions on Applied Superconductivity · 2016 · 19 citations · 11 references
EngineeringManufacturing EngineeringNuclear EngineeringElectromagnetismFusion EngineeringPlasma PhysicsFusion Reactor MaterialsMagnetic Confinement FusionNuclear FusionPlasma ConfinementSuperconducting Magnet SystemsTokamak EngineeringCoil DesignCompactionFusion Reactor EngineeringManufacturingSolenoid Coil DesignTokamak ConfinementTokamak PhysicsTokamak Plasmas
The China Fusion Engineering Test Reactor (CFETR) is a new tokamak device, whose magnet system includes the toroidal field, central solenoid (CS), and poloidal field coils. To develop the manufacturing technique for the full-size CS coil, the Central Solenoid Model Coil (CSMC) project was launched first. The cable-in-conduit conductor used for CFETR CSMC refers to the International Thermonuclear Experimental Reactor CS conductor with the same short twist pitch cable pattern. As the short twist pitch and low void fraction, a higher compaction ratio during cabling is required, and the possibility of damages occurring on strands is increased. After numerical analysis and experimental trials on cabling technology, one short cable sample was manufactured, which shows good results compared with former experimental cables.
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Challenges and status of ITER conductor production
A. Devred, I. Backbier, D. Bessette et al. · Superconductor Science and Technology · 2014 · 198 citations
Ken Tomabechi, J.R. Gilleland, Yu. A. Sokolov et al. · Nuclear Fusion · 1991 · 188 citations