Mechanical behaviour of ITER central solenoid
San Diego, CA（2009）
关键词
tokamak devices,fatigue,finite element analysis,fusion reactor design,fusion reactor divertors,niobium alloys,plasma toroidal confinement,stainless steel,superconducting coils,superconducting magnets,tin alloys,cc,cs,fecrcjk,iter magnet design,nb3sn,pf-coil,tf-coil,cable-in-conduit superconducting conductor,central solenoid,correction coils,divertor region,fatigue assessment,finite element analyses,jacket material,mechanical behaviour,poloidal field coils,pre-compression structure,stress levels,toroidal field coils,iter,magnets,component,stress,plasma stability,solenoids,magnetic flux,aluminum,materials
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