journal article·2006-06

Inert matrix fuel in dispersion type fuel elements

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

Journal of Nuclear Materials· Volume 352· Issue 1-3
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Abstract

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.
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Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Nuclear and radioactivity studies

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References (8)

Show source-provided references
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