Lessons Learned from the Design of ITER Internal Components
Fusion Engineering（2013）
Key words
Tokamak devices,cryostats,fusion reactor blankets,fusion reactor design,fusion reactor divertors,magnets,plasma boundary layers,plasma diagnostics,plasma flow,plasma toroidal confinement,plasma transport processes,tritium handling,ELM,FW plasma-facing-surface,ITER internal component design phases,ITER process,actively cooled components,balanced trade-off magnets,blanket modules,blanket vessel,breeding tritium reactor,coil set,complex openings,complex plasma diagnostics,complex routing,conceptual design phase,convective transport discovery,critical design consideration,critical design constraint,divertor components,engineering diagnostics,external component shielding,field lines,first wall,fusion device,heat flux,internal coils,internal component active cooling,internal cryostat,internal vessel,next generation fusion machines,operating state monitor,plasma duration,plasma equilibrium,plasma performance,plasma rotation control,plasma routing,plasma scrape-off layer,reserve space,resistive wall mode,traditional design sequence,traditional sequence,fusion reactor blanket components,fusion reactor design,plasma-facing component design,plasma-materials interactions
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