• DocumentCode
    2062822
  • Title

    Thermal design and analysis of DIII-D advanced divertor

  • Author

    Baxi, C.B. ; Reis, E. ; Smith, J.

  • Author_Institution
    Gen. Atomics, San Diego, CA, USA
  • fYear
    1989
  • fDate
    2-6 Oct 1989
  • Firstpage
    951
  • Abstract
    The DIII-D tokamak uses divertor plasma configurations to obtain enhanced plasma confinement. To further develop the divertor capability, a combined divertor baffle and electrically isolated toroidal-ring electrode will be installed. The high heat flux and elevated temperatures pose challenging design problems, especially for the insulating materials. The toroidal-ring support structure for the divertor is described. It must withstand a peak heat flux of 600 W/cm 2 for a period of 5 s. The results of a system analysis are presented. During operation, the advanced divertor is electrically biased relative to the vessel. To provide cross field electrical insulation between the divertor and the vessel, parts of the shelf and the floor tiles will be fabricated from nonconducting materials which will be subjected to both high heat flux and a high-temperature environment. To obtain an acceptable design, thermal analyses were performed to calculate the temperature differences between the divertor structure and the vessel wall during periods of bakeout and during plasma operation. A number of finite-element thermal stress analyses of individual components were done to ensure acceptable temperatures and stresses
  • Keywords
    Tokamak devices; finite element analysis; fusion reactor materials; fusion reactor theory and design; thermal stresses; 5 s; DIII-D tokamak; cross field electrical insulation; divertor; divertor baffle; finite-element thermal stress analyses; system analysis; thermal design; tiles; toroidal-ring electrode; toroidal-ring support structure; Dielectrics and electrical insulation; Electrodes; Performance analysis; Plasma confinement; Plasma materials processing; Plasma temperature; Resistance heating; Thermal stresses; Tiles; Tokamaks;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
  • Conference_Location
    Knoxville, TN
  • Type

    conf

  • DOI
    10.1109/FUSION.1989.102374
  • Filename
    102374