Coprocessed nuclear fuels containing (U, Pu) values as oxides, c

Details Coprocessed nuclear fuels containing (U, Pu) values as oxides, c Coprocessed nuclear fuels containing (U, Pu) values as oxides, c

1981-01-09

1983-08-09

Kyle, Deborah L.

Compositions

Radioactive compositions

252634, 252635, 252642, 252643, G21C 1946

Patent

active

043977782

ABSTRACT:
Method for direct coprocessing of nuclear fuels derived from a product stream of a fuels reprocessing facility containing uranium, plutonium, and fission product values comprising nitrate stabilization of said stream vacuum concentration to remove water and nitrates, neutralization to form an acid deficient feed solution for the internal gelation mode of sol-gel technology, green spherule formation, recovery and treatment for loading into a fuel element by vibra packed or pellet formation technologies.

REFERENCES:
patent: 3862908 (1975-01-01), Fitch et al.
patent: 4231976 (1980-11-01), Bischoff et al.
patent: 4278559 (1981-07-01), Levenson et al.
Bischoff et al., "Sol-Gel Process for Carbide Production", EIR Report No. 236 (1973).

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