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U.S. Department of Energy
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Preparation of filterable coprecipitate of plutonium and uranium (in Danish)

Patent ·
OSTI ID:4411460

A process is described for producing a homogeneous plutonium oxide- uranium oxide fuel for a nuclear reactor. An easily filtered hydrous oxide mixture of plutonium and uranium is coprecipitated from an acidic feed solution containing plutonium and uranium in a mole concentration ratio between about 0.7 and 1.5 by the addition of ammonium hydroxide. The precipitate is washed, dried, and reduced in a hydrogen atmosphere, then mixed and blended with reactor-grade uranium oxide to adjust the plutonium-- uraniurm ratio to the desired value. (DE)

Research Organization:
Originating Research Org. not identified
NSA Number:
NSA-29-008223
OSTI ID:
4411460
Report Number(s):
DK 125584
Country of Publication:
Denmark
Language:
Danish