Method of manufacturing nuclear fuel pellet by recycling...

G - Physics – 21 – C

Patent

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Details

G21C 19/44 (2006.01) G21C 21/00 (2006.01)

Patent

CA 2254489

This invention provides a method of manufacturing new oxide fuel pellets by recycling irradiated UO2 or (U,Pu)O2 fuel pellets. Irradiated UO2 fuel pellets are oxidized so as to make U3O8-based powder containing fission products, and then the U3O8-based powder is mixed with an additive, which is an oxide or a compound containing an element selected from the group consisting of niobium, titanium, vanadium, aluminum, magnesium, chromium, silicon, lithium, and mixtures thereof. Green pellets are formed from the mixed powder comprising the U3O8-based powder and the additive, and then sintered at 1500 °C or higher in a reducing gas atmosphere to produce UO2-based fuel pellets with high densities.

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