• DocumentCode
    3460344
  • Title

    Divertor Heat Loads from Thermal and Alpha Particles in a Compact Stellarator Reactor

  • Author

    Mau, T.K. ; Kaiser, T.B. ; Lyon, J.F. ; Maingi, R. ; Raffray, A.R. ; Wang, X. ; Ku, L.P. ; Zarnstorff, M.

  • Author_Institution
    Univ. of California at San Diego, La Jolla
  • fYear
    2007
  • fDate
    17-21 June 2007
  • Firstpage
    1
  • Lastpage
    4
  • Abstract
    Divertor heat load distributions due to thermal and alpha particles have been assessed in an NCSX-based compact stellarator reactor. A divertor plate system is envisaged, with 4 plates per field period and covering 7% of the plasma surface area. The field-line tracing technique is employed; for thermal flux, the conventional approach is used, while for alphas, their characteristic exit pattern from the plasma and subsequent gyro- orbits are approximated. For the ARIES-CS reference design point (R=7.75 m, A=4.5, B=5.7 T, beta=6.4% and Pnet=1000 MW), combined peak heat loads in the 5 -18 MW/m2 range on the plates have been obtained, assuming a 75% radiation fraction both in the core and at the edge, and a 5% alpha loss fraction. The alpha heat flux could be a dominant determining factor. Further optimization study is warranted to lower all peak heat loads to satisfy the accepted limit of les10 MW/m2.
  • Keywords
    fusion reactor design; fusion reactor divertors; plasma toroidal confinement; stellarators; ARIES-CS reference design point; NCSX-based compact stellarator reactor; alpha particles; core energy confinement; divertor heat loads; divertor plate system; field-line tracing technique; gyroorbits; optimization study; plasma surface area; radiation fraction; thermal particles; toroidal length; Alpha particles; Inductors; Laboratories; Plasma confinement; Plasma density; Plasma properties; Plasma stability; Plasma transport processes; Temperature control; Thermal loading; alpha particles; divertor; heat load; reactor; stellarator;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 2007. SOFE 2007. 2007 IEEE 22nd Symposium on
  • Conference_Location
    Albuquerque, NM
  • Print_ISBN
    978-1-4244-1193-1
  • Electronic_ISBN
    978-1-4244-1194-8
  • Type

    conf

  • DOI
    10.1109/FUSION.2007.4337872
  • Filename
    4337872