• DocumentCode
    1603007
  • 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
  • fYear
    2013
  • Firstpage
    1
  • Lastpage
    4
  • 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;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
  • Conference_Location
    San Francisco, CA
  • Print_ISBN
    978-1-4799-0169-2
  • Type

    conf

  • DOI
    10.1109/SOFE.2013.6635281
  • Filename
    6635281