Irradiated fuel reprocessing

Details Irradiated fuel reprocessing Irradiated fuel reprocessing

1975-05-27

1977-03-08

Miller, Edward A.

Chemistry of inorganic compounds

Treating mixture to obtain metal containing compound

Radioactive metal

423 7, 423 8, 423 10, C01G 4300

Patent

active

040112969

ABSTRACT:
A process for separately recovering uranium, plutonium and neptunium substantially free of fission products from irradiated nuclear fuel is presented in which the fuel is dissolved in a strong mineral acid forming an aqueous dissolved nuclear fuel solution and treated to separate the uranium, plutonium and neptunium therefrom substantially free of said fission products by the sequential steps of solvent extraction, ion exchange and fluorination. The process has an improvement comprising the addition of a sufficient quantity of an additive of a stable metallic complex to the aqueous dissolved nuclear fuel solution prior to solvent extraction. This achieves improved purity of the separated uranium, plutonium and neptunium.

REFERENCES:
patent: 3208819 (1965-09-01), Wallace
patent: 3374068 (1968-03-01), Erlandson et al.
patent: 3432276 (1969-03-01), Reas
patent: 3574531 (1971-04-01), Schulz
patent: 3825649 (1974-07-01), Gresky et al.
patent: 3867510 (1975-02-01), Miller et al.

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