Method for producing mixed-oxide nuclear fuel pellets...

G - Physics – 21 – C

Patent

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G21C 3/62 (2006.01)

Patent

CA 1169643

ABSTRACT OF THE DISCLOSURE Production of mixed-oxide nuclear fuel pellets of uranium dioxide (UO2+x) and plutonium dioxide (PuO2) which are soluble in nitric acid. The powder mixture to a halogen-free milling aid has been added, is milled and sub- sequently granulated, pressed and sintered. The milling aid is expelled by subsequent drying processes or heat treatments (sintering). The milling pro- cess is controlled to obtain a primary grain size of less than two micro- meters.

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