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Conceptual Design of Fusion Experimental Reactor(FER)
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1983
Year
EngineeringFusion Experimental ReactorDesignFusion PowerDense PlasmaNext Generation TokamakMagnetohydrodynamicsFusion EnergyControlled Nuclear FusionPropulsionNuclear Reactor DesignFusion System DesignMagnetic Confinement FusionTritium Breeding Ratio
Conceptual design studies of the Fusion Experimental Reactor (FER) have been performed. The FER has an objective of achieving self-ignition and demonstrating engineering feasibility as a next generation tokamak to JT-60. Various concepts of the FER have been considered. The reference design is based on a double-null divertor. Optional design studies with some attractive features based on advanced concepts such as pumped limiter and RF current drive have been carried out. Key design parameters are; fusion power of 440 MW, average neutron wall loading of 1MW/m2, major radius of 5.5m, plasma minor radius of 1.1m, plasma elongation of 1.5, plasma current of 5.3MA, toroidal beta of 4%, toroidal field on plasma axis of 5.7T and tritium breeding ratio of above unity.