Overview of the Physics and Engineering Design of NSTX Upgrade
Nuclear Fusion（2012）
Key words
Tokamak devices,fusion reactor design,fusion reactor divertors,plasma heating,plasma toroidal confinement,plasma transport processes,NBI heating power,NSTX upgrade,National Spherical Torus experiment,aspect ratio,compact size configuration,diffusion times,engineering design,fusion neutron fluences,fusion nuclear science facility,heat-flux width,modular configuration,noninductive current fractions,nonsolenoidal current ramp-up,normalized confinement scaling,physics design,plasma beta active control,plasma current,plasma transport research,resistive wall mode control,snowflake divertor configuration,spherical tokamak,tangential injection,toroidal field
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