In the thorium fuel cycle, it is necessary to breed fissile 233U from fertile and naturally available 232Th to produce the energy dense material required for power generation.  As 233U fissions, neutron siphoning fission products build-in.  Eventually a separation of the 233U fuel from the fission products as well as the remaining thorium is necessary to reestablish an environment that favors 233U fission. These separations are conventionally examined using solvent extraction technologies due the relatively cost-effective and high throughput nature of the technique.  However; sometimes a final cleanup of uranium after bulk solvent extraction purification is appropriate.  In these instances, extraction chromatographic separations may prove more advantageous.  This presentation will discuss the development and application of extraction chromatographic materials for the separation of uranium from thorium.  Results examining the kinetics and distribution of f-elements in batch contacts with the developed material will be discussed.

Extraction chromatographic materials for selective recovery of uranium in a thorium nuclear fuel cycle

247th National Meeting (2014)

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