Method of separating and purifying spent solvent generated in nu

Details Method of separating and purifying spent solvent generated in nu Method of separating and purifying spent solvent generated in nu

1991-03-22

1992-05-05

Hunt, Brooks H.

Compositions

Radioactive compositions

210774, 210806, 203 91, 203 48, 585812, 562608, G21F 900

Patent

active

051105071

ABSTRACT:
A method of separating and purifying a spent solvent generated in a nuclear fuel cycle and containing a phosphate and a higher hydrocarbon. This method comprises treating the spent solvent at a temperature not greater than the freezing point of the higher hydrocarbon but not less than the freezing point of the phosphate to selectively freeze the higher hydrocarbon, and separating a resulting frozen solid mainly composed of the higher hydrocarbon from a remaining solution containing the phosphate in a higher concentration. The remaining solution may further be subjected to low-temperature vacuum distillation to separate the solution into the phosphate and a deterioration product thereof.

REFERENCES:
patent: 2752230 (1956-06-01), Findlay
patent: 2813099 (1957-11-01), Weedman
patent: 3205588 (1965-09-01), Oetjen et al.
patent: 3361649 (1968-01-01), Karter
patent: 4981616 (1991-01-01), Ohtsuka et al.

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