Showing papers by "Satoshi Nishio published in 1983"

Conceptual design of Fusion Experimental Reactor (FER)

Abstract: Conceptual design studies of the Fusion Experimental Reactor (FER) have been performed The FER has an objective of achieving selfignition 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/m/sup 2/, major radius of 55m, plasma minor radius of 11m, plasma elongation of 15, plasma current of 53MA, toroidal beta of 4%, toroidal field on plasma axis of 57T and tritium breeding ratio of above unity