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Preparation of mixed oxide nuclear fuel

Patent ·
OSTI ID:7310968

A method is described for the preparation of UO/sub 2/-PuO/sub 2/ nuclear fuel pellets. Green pellets of the basic fuel material, UO/sub 2/, are fabricated by standard powder metallurgy techniques. After sintering at a temperature of 1100 to 1400/sup 0/C, the pellets are ground or machined to a suitable size prior to impregnation with a plutonium salt solution. After impregnation, sintering of the pellets at 1400 to 1700/sup 0/C converts the plutonium salt to PuO/sub 2/. (BLM)

Assignee:
Atomic Energy of Canada Ltd.
Patent Number(s):
US 4020131
OSTI ID:
7310968
Country of Publication:
United States
Language:
English

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Related Subjects

050700* -- Nuclear Fuels-- Fuels Production & Properties
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 MATERIALS SCIENCE
360201 -- Ceramics
Cermets
& Refractories-- Preparation & Fabrication
ACTINIDE COMPOUNDS
CHALCOGENIDES
FABRICATION
FUEL PELLETS
MACHINING
METALLURGY
OXIDES
OXYGEN COMPOUNDS
PELLETS
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
POWDER METALLURGY
SINTERING
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES