Decontamination of Carbonate Containing Process Streams in Nuclear Fuel Reprocessing by Ion Exchange Chromatography

Author:

Faubel Werner1,Ali Sameh A.1

Affiliation:

1. Kernforschungszentrum Karlsruhe Institut für Radiochemie, Postfach 3640, 7500 Karlsruhe Federal Republic of Germany

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference15 articles.

1. W. B. LANHAM and T. C. RUNION, “Purex Process for Plutonium and Uranium Recovery,” ORNL-479, Oak Ridge National Laboratory (1949).

2. R. G. WYMER and B. L. VONDRA, Eds. Light Water Reactor Nuclear Fuel Cycle, CRC Press, Boca Raton, Florida (1981).

3. J. HAAG and SAMEH A. ALI, “Dynamic Experiments on the Separation of Uranium Tricarbonate Ions on Three Different Anion Exchangers and Studies of the Elution Properties,” KfK-3015, Karlsruhe Nuclear Research Center (1981).

4. J. HAAG, “Separation of Actinides and Fission Products from Carbonate Containing Process Streams,”KfK-3460, Karlsruhe Nuclear Research Center (1983).

5. Uranium solution-mineral equilibria at low temperatures with applications to sedimentary ore deposits

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1. Recovery treatment of nonfissioned uranium in the production of99Mo;Journal of Radioanalytical and Nuclear Chemistry Articles;1994-03

2. Decontamination treatment of uranium in tricarbonated solutions;Journal of Radioanalytical and Nuclear Chemistry Letters;1993-04

3. Partitioning of Nitric Acid Intermediate-Level Waste Solutions by Sorption;Nuclear Technology;1989-07

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