Leach apparatus including means to protect ion exchange resin

Chemical apparatus and process disinfecting – deodorizing – preser – Chemical reactor – For radioactive reactant or product

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422189, 422234, F04C 2900

Patent

active

044951523

ABSTRACT:
An apparatus for recovering uranium and/or related values which include means for protecting ion-exchange resins in the recovery operation from oxidative degradation due to contact with hydrogen peroxide. A guard chamber is positioned in the elution circuit so that barren eluant, after it is stripped of its uranium and/or related values by treatment with hydrogen peroxide, will flow through the chamber. The guard chamber contains catalytic material, e.g. activated carbon, which decomposes hydrogen peroxide upon contact into water and oxygen. The barren eluant, after it passes through the catalytic material, is used to make up fresh eluant for reuse in the recovery method without the risk of the fresh eluant causing oxidative degradation of the resins.

REFERENCES:
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patent: 3288570 (1966-11-01), Henrickson
patent: 4024215 (1977-05-01), Caropreso et al.
patent: 4098691 (1978-07-01), Filby
patent: 4105253 (1978-08-01), Showalter
patent: 4110204 (1978-08-01), Farmer
patent: 4116488 (1978-09-01), Hsueh et al.
patent: 4155982 (1979-05-01), Hunkin et al.
Merritt, "The Extractive Metallurgy of Uranium", pp. 247-248, Colorado School of Mines, (1971).
Hurst et al., "Progress and Problems of Recovering Uranium from Wet Process Phosphoric Acid", ORNL, paper presented at 26th Ann. Meeting, Fertilizer Industry Roundtable, Atlanta, Ga. (Oct. 1976).

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