Advanced aqueous reprocessing in P&T strategies: Process demonstrations on genuine fuels and targets
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Birgit Christiansen
Summary
In the present work the performance of several processes used for advanced reprocessing of commercial LWR fuels as well as transmutation targets is compared. As a first step uranium and plutonium were recovered by PUREX type reprocessing. The raffinate, containing fission products including lanthanides and the minor actinides (MA) was used as feed for the second step in which minor actinides and lanthanides were separated from the bulk of the fission products. The five different processes tested use CMPO, DIDPA, TRPO, Diamide and CYANEX 923 as extractants. In the third step MA are separated from lanthanides. Here three processes were tested, i.e. using CYANEX 301, the synergistic mixture of di-chloro substituted CYANEX 301 and TOPO, and BTP solvents. Column-, batch- and continuous counter-current extraction techniques were used for the tests. The different processes will be described and discussed in terms of performances and efficiencies for Am and Cm separation. Efficient separation of MA from different genuine fuel solutions could be demonstrated and thereby also the possibility of closing a future transmutation fuel cycle. The combination of Diamide and BTP seems to be the best, among extractants tested, to achieve an efficient MA recovery from spent fuel.
© 2004 Oldenbourg Wissenschaftsverlag GmbH
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- Uranium association with halophilic and non-halophilic bacteria and archaea
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- Fluorescence and IR studies on the hydration state of lanthanides(III) and curium(III) in the complexes extracted with purified Cyanex301, Cyanex302 and Cyanex272
- Synthesis and characterization of uranium(VI) and thorium(IV) complexes with o-hydroxy N,N´-dimethylbenzylamine and o-carboxy N,N´-dimethylbenzylamine
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Articles in the same Issue
- Experimental studies and nuclear model calculations on (p, xn) and (p, pxn) reactions on 85Rb from their thresholds up to 100 MeV
- Theoretical treatment of the complexation of element 106, Sg, in HF solutions
- Extraction and separation of Am(III) and Sr(II) by N,N,N´,N´-tetraoctyl-3-oxapentanediamide (TODGA)
- Method for determining plutonium in air filters in detection of nuclear activities
- Advanced aqueous reprocessing in P&T strategies: Process demonstrations on genuine fuels and targets
- Uranium association with halophilic and non-halophilic bacteria and archaea
- Complex formation of uranium(VI) in periodate solutions
- Fluorescence and IR studies on the hydration state of lanthanides(III) and curium(III) in the complexes extracted with purified Cyanex301, Cyanex302 and Cyanex272
- Synthesis and characterization of uranium(VI) and thorium(IV) complexes with o-hydroxy N,N´-dimethylbenzylamine and o-carboxy N,N´-dimethylbenzylamine
- Ion exchange and chromatographic separation of cesium, strontium and europium from acidic streams using uranium antimonate
- Investigations on adsorption and transport behaviour of carrier-free silver, gold and platinum in quartz columns under vacuum conditions
