Liquid purification or separation – Processes – Ion exchange or selective sorption
Patent
1991-10-11
1994-03-29
Cintins, Ivars
Liquid purification or separation
Processes
Ion exchange or selective sorption
210682, 210751, 252628, 252631, 588257, C02F 142
Patent
active
052981665
ABSTRACT:
Plutonium, strontium, and cesium found in aqueous waste solutions resulting from nuclear fuel processing are removed by contacting the waste solutions with synthetic zeolite incorporating up to about 5 wt % titanium as sodium titanate in an ion exchange system. More than 99.9% of the plutonium, strontium, and cesium are removed from the waste solutions.
REFERENCES:
Lynch, R. W., R. G. Dosch, B. T. Kenna, J. K. Johnstone, and E. J. Nowak, 1975, The Sandia Solidification Process-A Broad Range Aqueous Waste Solidification Method, IAEA-SM-207175, Sandia Laboratories, Albuquerque, NM.
Dosch, R. G. 1978, The Use of Titanates in Decontamination of Defense Wastes, SAND78-0710, Sandia Laboratories, Albuquerque, NM.
Schulz, W. W. 1978, Decontamination of Hanford Plutonium Reclamation Facility Salt Waste Solution, RHO-SA-23, Rockwell Hanford Operations, Richland, Wash.
Bray, L. A., L. K. Holton, T. R. Myers, G. M. Richardson, and B. M. Wise, 1084, Experimental Data Developed to Support the Selection of a Treatment Process for West Valley Alkaline Supernatant, PNL-4969, Pacific Northwest Laboratory, Richland, Wash.
Bray Lane A.
Burger Leland L.
Battelle (Memorial Institute)
Cintins Ivars
Hauth Joseph J.
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