Title :
NSTX-U Vacuum Vessel design modification
Author :
Atnafu, Neway D. ; Denault, M. ; Dudek, L. ; Gerhardt, S. ; Labik, G. ; Smith ; Stevenson, Tim ; Titus, P.
Author_Institution :
Princeton Plasma Phys. Lab., Princeton, NJ, USA
Abstract :
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.
Keywords :
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; Coils; Laser beams; Plasmas; Scattering; Stress; Welding; NSTX-U; port; reinforcement; stress; vacuum vessel; weldment;
Conference_Titel :
Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
Conference_Location :
San Francisco, CA
Print_ISBN :
978-1-4799-0169-2
DOI :
10.1109/SOFE.2013.6635281