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
Link To Document :
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