Method of regulating a purex solvent extraction process

Details Method of regulating a purex solvent extraction process Method of regulating a purex solvent extraction process

1989-03-31

1991-03-19

Miller, Edward A.

Chemistry of inorganic compounds

Treating mixture to obtain metal containing compound

Radioactive metal

423 4, 423 211, 252631, 364558, B01D 1100

Patent

active

050009273

ABSTRACT:
The "Purex" solvent extraction and separation process for recovering uranium from scrap material or spent fuel containing gadolinia is modified by treating uranium containing scrap or spent fuel with nitric acid to convert uranium oxide to soluble uranyl nitrate in an aqueous medium, separating the uranyl nitrate from the aqueous media with an organic medium containing tri-butyl phosphate, and then releasing the separated uranium from the organic medium with water. The improvement comprises monitoring the density of the organic medium and controlling the feed rate of the uranium in the aqueous medium in response to the density measurements.

REFERENCES:
patent: 2979379 (1961-04-01), Schmieding et al.
patent: 2990240 (1961-06-01), Ellison et al.
patent: 4595529 (1986-06-01), Neace
patent: 4758313 (1988-07-01), Schmieder et al.
Hanson, Mills, A. L., Recent Advances in Liquid-Liquid Extraction, 1971, pp. 186-196.

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