NSTX-U Vacuum Vessel design modification

Fusion Engineering(2013)

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摘要
The NSTX-U requirements will double the Toroidal Field (TF), Plasma Current (Ip), Beam Injection Power, and extend pulse length. The larger centerstack requires re-aiming of the Multi Pulse Thomson Scattering (MPTS) lasers and Vacuum Vessel (VV) modifications at Bay L. The second neutral beam requirements include larger tangency radii and thus a VV modification at Bay K and Bay J. A cap design for a new weldment was developed to achieve these larger beam trajectories without losing the utility of the Bay J port for diagnostics. Analyses of loads indicated the need for reinforcements of the vessel at the midplane. NSTX has 6 picture frame type Resistive Wall Mode (RWM) coils around the exterior circumference of the vacuum vessel; each coil surrounds pairs of ports. The modifications needed for the upgrade were intended to minimize the impact to the RWM fields at the plasma. A Pro E global model segment was used to model the vacuum vessel. ANSYS was used to apply loads and investigate reinforcement configurations. A focused effort and analysis produced a design capable of achieving the desired performance of the upgrade while maintaining utility and continuity of RWM coil physics pre- and post-upgrade physics performance. The installation of the Bay J-K and Bay L Port Caps was completed and the reinforcing weldments have been partially installed.
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关键词
tokamak devices,fusion reactor design,plasma beam injection heating,plasma toroidal confinement,plasma transport processes,plasma-wall interactions,ansys,bay j-k port cap,bay l port cap,nstx-u vacuum vessel design modification,pro e global model segment,beam injection power,beam trajectories,multipulse thomson scattering lasers,plasma current,plasma diagnostics,reinforcement configurations,resistive wall mode coils,second neutral beam requirements,tangency radii,toroidal field,vacuum vessel exterior circumference,nstx-u,port,reinforcement,stress,vacuum vessel,weldment,plasmas,welding,scattering
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