Spent fuel treatment method

Details Spent fuel treatment method Spent fuel treatment method

1989-08-29

1991-01-01

Miller, Edward A.

Compositions

Radioactive compositions

Nuclear reactor fuel

252631, 252364, 210770, 210774, 423 10, G21F 904

Patent

active

049816160

ABSTRACT:
In a method for recovering plutonium and uranium from spent nuclear fuel by solvent extraction having solvent consisting of tri-n-butyl phosphate, dibutyl phosphate and n-dodecane, the improvement comprises separating the n-dodecane from the phosphate by freeze-drying and separating the phosphate from each other and residual impurities by fractional distillation.

REFERENCES:
patent: 3205588 (1965-09-01), Oetjen et al.
patent: 3281371 (1966-10-01), Nerge et al.
patent: 3361649 (1968-01-01), Karter
patent: 3725293 (1973-04-01), Haas
patent: 4043936 (1977-08-01), Francis et al.
patent: 4225455 (1980-09-01), Haas
patent: 4364859 (1982-12-01), Ohtsuka et al.
patent: 4444723 (1984-04-01), Matsumaru et al.

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