• DocumentCode
    3168835
  • Title

    An improved first stability advanced fuel tokamak Apollo-L3

  • Author

    Emmert, G.A. ; Kulcinski, G.L. ; Blanchard, J.P. ; El-Guebaly, L.A. ; Khater, H. ; Maynard, C.W. ; Mogahed, E.A. ; Santarius, J.F. ; Sawan, M.E. ; Sviatoslavsky, I.N. ; Wittenberg, L.J.

  • Author_Institution
    Fusion Technol. Inst., Wisconsin Univ., Madison, WI, USA
  • fYear
    1991
  • fDate
    30 Sep-3 Oct 1991
  • Firstpage
    1106
  • Abstract
    The Apollo-L3 conceptual reactor design utilizes D-3He fuel in a first stability tokamak configuration with direct conversion of synchrotron radiation to electricity as well as thermal conversion of surface heat and neutron energy. An update of the parameters of the design is given, and analyses of certain critical issues of Apollo-L3 are reported. These include plasma startup, loss of fast ions by magnetic ripple, safety analyses, and tritium storage. The update has led to an increase in the major radius by about 40 cm and an increase in the cost of electricity by about 10%. An alternative to direct energy conversion of the synchrotron radiation is to convert the energy using a thermal cycle; this increases the cost by another 10%. Startup of the plasma using a small amount of tritium eliminates the need for auxiliary heating other than that provided by the current drive system. Analysis of accident scenarios led to a possible offsite early dose of 3.6 rem for a LOCA without burning of the organic coolant and 103 rem if the organic coolant burns. On the basis of the expected temperature of the shield in a LOCA accident and the radioactive inventory, Apollo-L3 qualifies for a level of safety rating of one
  • Keywords
    accidents; fusion reactor fuel; fusion reactor operation; fusion reactor safety; fusion reactor theory and design; plasma heating; plasma toroidal confinement; Apollo-L3; D-3He; LOCA; T; accident; auxiliary heating; burning; conceptual reactor design; critical issues; direct conversion; electricity; fast ions; first stability advanced fuel tokamak; fuel; loss; magnetic ripple; neutron energy; offsite early dose; organic coolant; plasma startup; radioactive inventory; safety analyses; safety rating; shield; storage; surface heat; synchrotron radiation; thermal conversion; Accidents; Coolants; Costs; Energy conversion; Fuels; Inductors; Magnetic analysis; Stability; Synchrotron radiation; Tokamaks;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1991. Proceedings., 14th IEEE/NPSS Symposium on
  • Conference_Location
    San Diego, CA
  • Print_ISBN
    0-7803-0132-3
  • Type

    conf

  • DOI
    10.1109/FUSION.1991.218678
  • Filename
    218678