• Title of article

    Inert matrix fuel in dispersion type fuel elements

  • Author/Authors

    Savchenko، نويسنده , , A.M. and Vatulin، نويسنده , , A.V. and Morozov، نويسنده , , A.V. and Sirotin، نويسنده , , V.L. and Dobrikova، نويسنده , , I.V. and Kulakov، نويسنده , , G.V. and Ershov، نويسنده , , S.A. and Kostomarov، نويسنده , , V.P. and Stelyuk، نويسنده , , Y.I.، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2006
  • Pages
    6
  • From page
    372
  • To page
    377
  • Abstract
    The advantages of using inert matrix fuel (IMF) as a dispersion fuel in an aluminium alloy matrix are considered, in particular, low temperatures in the fuel centre, achievable high burn-ups, serviceability in transients and an environmentally friendly process of fuel rod fabrication. Two main versions of IMF are under development at A.A. Bochvar Institute, i.e. heterogeneous or isolated distribution of plutonium. The out-of-pile results on IMF loaded with uranium dioxide as plutonium simulator are presented. Fuel elements with uranium dioxide composition fabricated at A.A. Bochvar Institute are currently under MIR tests (RIAR, Dimitrovgrad). The fuel elements reached a burn-up of 88 MW d kg−1 (equivalent to the burn up of the standard uranium dioxide pelletized fuel) without loss of leak-tightness of the cladding. The feasibility of fabricating IMF of these particular types with plutonium dioxide is considered with a view to in-pile irradiation.
  • Journal title
    Journal of Nuclear Materials
  • Serial Year
    2006
  • Journal title
    Journal of Nuclear Materials
  • Record number

    1363775