Method of separating and purifying spent solvent generated in nu

Hazardous or toxic waste destruction or containment – Destruction or containment of radioactive waste – Treating radioactive liquid

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210808, 203 48, G21F 900

Patent

active

055235158

ABSTRACT:
A method of separating and purifying a spent solvent generated in a nuclear fuel cycle and containing a higher hydrocarbon and a phosphate. This method comprises applying to the spent solvent a pressure high enough for allowing the crystallization of the higher hydrocarbon to thereby crystallize the higher hydrocarbon, and separating under pressure a resulting 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 contained in the solution.

REFERENCES:
patent: 4784766 (1988-11-01), Moritoki et al.
patent: 5019658 (1991-05-01), Cahn
patent: 5082635 (1992-01-01), Wakatsuki et al.
patent: 5110507 (1992-05-01), Ohtsuka et al.

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