• DocumentCode
    2733204
  • Title

    Structural analysis of the TPX plasma facing components

  • Author

    Reis, E.E. ; Chin, E. ; Redler, K. ; Williams, F.R.

  • Author_Institution
    Gen. Atomics, San Diego, CA, USA
  • Volume
    2
  • fYear
    1993
  • fDate
    11-15 Oct 1993
  • Firstpage
    1197
  • Abstract
    Structural design calculations and finite element analyses of the conceptual designs of the Tokamak Physics Experiment (TPX) divertor and inboard limiter were performed for thermal and electromagnetic induced mechanical loads. Finite element analyses of the divertor and inboard limiter support structures were performed for loads due to halo currents and eddy currents due to a plasma disruption. The results show the conceptual designs satisfy primary stress allowables. A number of scoping studies were performed to evaluate the thermal and structural response of various tile materials and designs for the TPX divertor. The purpose of these studies was to investigate what possible gains would occur if the present design requirements for the heat flux surfaces were eased. The studies were performed for beryllium and various carbon-carbon materials brazed to a dispersion strengthened copper tube. The studies included the effects of a soft copper compliant layer of varying thicknesses interfacing the copper tube and the tile. Elastic-plastic thermal stress analyses were performed of 1D, 2D, and 4D carbon-carbon and beryllium monoblock designs and for a saddleblock design with 1D carbon-carbon. The residual stresses and amount of plastic straining in the copper tube during the braze cycle are accounted for in computing the stress state after the brazing process and during steady state operating conditions
  • Keywords
    Tokamak devices; beryllium; carbon fibre reinforced composites; copper; eddy currents; elastoplasticity; finite element analysis; fusion reactor design; fusion reactor materials; fusion reactor operation; fusion reactors; thermal stresses; Be; C-C; Cu; TPX divertor; TPX plasma facing components; Tokamak Physics Experiment; composite materials; conceptual designs; dispersion strengthened tube; eddy currents; elastic-plastic thermal stress analyses; electromagnetic induced mechanical loads; finite element analyses; fusion reactor; heat flux surfaces; inboard limiter; monoblock designs; plasma disruption; plastic straining; scoping studies; soft compliant layer; steady state operating conditions; structural design calculations; thermal induced mechanical loads; tile materials; Copper; Electromagnetic analysis; Finite element methods; Performance analysis; Physics; Plasmas; Residual stresses; Thermal stresses; Tiles; Tokamaks;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
  • Conference_Location
    Hyannis, MA
  • Print_ISBN
    0-7803-1412-3
  • Type

    conf

  • DOI
    10.1109/FUSION.1993.518537
  • Filename
    518537