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MOX fuel
A used MOX, which has 63 GW days (thermal) of burnup and has been examined with a scanning electron microscope using electron microprobe attachment. T
A used MOX, which has 63 GW days (thermal) of burnup and has been examined with a scanning electron microscope using electron microprobe attachment. The lighter the pixel in the right hand side the higher the plutonium content of the material at that spot
Fabrication process for mixed oxide fuel.
Fabrication process for mixed oxide fuel.
UO2lattice
UO2lattice
Uranium dioxide
Uranium dioxide
Sintered uranium dioxide pellet
Sintered uranium dioxide pellet
Starting material containers for uranium dioxide fuel pellet production at a plant in Russia
Starting material containers for uranium dioxide fuel pellet production at a plant in Russia