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For some time now, the Institut für Radiochemie, as part of its Reprocessing and Waste Treatment Project, has been developing chromatographic methods for the selective decontamination of individual process streams and testing these methods under relevant conditions. In particular, a procedure has been developed to decontaminate the carbonate wash of the extraction medium (tributyl phosphate dissolved in kerosene) issuing from the PUREX process. It takes advantage of the fact that the actinides react with carbonates to form highly stable compounds which can be retained by weakly alkaline anionic exchangers, giving a load up to 300g uranium per kg of resin. After successful decontamination of the individual partial streams, the limits of chromatography are questioned with particular regard to solutions with very high salt content in the ILW concentrates of the Kernforschungszentrum Karlsruhe. The aim of the work has, therefore, been to develop the chromatographic procedures further to make them suitable for decontamination of these ILW concentrates.

Additional information

Authors: FAUBEL W, Kernforschungszentrum Karlsruhe GmbH, Karlsruhe (DE);MEHRET R, Kernforschungszentrum Karlsruhe GmbH, Karlsruhe (DE);MENZLER P-M, Kernforschungszentrum Karlsruhe GmbH, Karlsruhe (DE)
Bibliographic Reference: EUR 12911 DE (1990) 75 pp., FS, ECU 7.50
Availability: (2)
ISBN: ISBN 92-826-1622-3
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