Method of recovering neptunium from spent nuclear fuel

Details Method of recovering neptunium from spent nuclear fuel Method of recovering neptunium from spent nuclear fuel

1973-10-05

1976-06-08

Padgett, Benjamin R.

Chemistry of inorganic compounds

Treating mixture to obtain metal containing compound

Radioactive metal

423250, C01G 5600

Patent

active

039624013

ABSTRACT:
An improved Purex wet recovery process including the step of extracting and separating uranium and plutonium simultaneously from the fission products in the presence of nitric acid and nitrous acid by using a multistage extractor unit having an extracting section and a washing section is provided for separating and recovering neptunium simultaneously with uranium and plutonium contained in spent nuclear fuel. The improved method comprises the steps of maintaining the nitrous acid concentration in said extracting section at a level suited for effecting oxidation of neptunium from (V) to (VI) valence, while lowering the nitrous acid concentration in said washing section so as to suppress reduction of neptunium from (VI) to (V) valence, and maintaining the nitric acid concentration in said washing section at a high level.

REFERENCES:
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patent: 3714324 (1973-01-01), Weech
Gourisse (I), Nuclear Science Abstracts, 26, 2426, Abs. No. 25412, (June 1972).
Nuclear Science Abstracts, 25, 3166, Abs. No. 32040, (July 1971).
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Gourisse (II), Nuclear Science Abstracts, 25, 399, Abs. No. 4135, (1971).
Srinivasan et al. (II), Nuclear Science Abstracts, 26, p. 2971, Abs. No. 30929 and 30930, (1972).

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