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Partitioning of liquid high-level radioactive waste (HLW) was studied as an option of facilitating the final waste disposal. A flowsheet of a solvent extraction partitioning process was proposed. Pu(IV), Np(VI), Zr(IV), Tc(VII), and U(VI) are extracted in the first cycle of the process with tributyl phosphate. Selective back extraction yields two product fractions, one of them containing Zr and Tc and the other containing Pu, Np and U. Transplutonides(III) are extracted in the second process cycle together with lanthanides(III) by octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO).
A compilation of data related to the separation of actinides and fission products from the HLW was performed in the first stage of the work. A review was written and conclusions were drawn about the choice of promising methods applicable in a partitioning process.
Work on the second partitioning cycle concerned search for an alternative modifier for the CMPO extractant, and attainment of a high decontamination factor for Am. Main attention was paid to the investigation of extractants for selective extraction of transplutonides(III) over lanthanides(III), performed with Am(III) and Eu(III) as representatives of the two element groups. The required selectivity is reached in the extraction of thiocyanates by CMPO. .

Additional information

Authors: KOLARIK Z, Forschungszentrum Karlsruhe GmbH, Institut für Technische Chemie (DE);SCHULER R, Forschungszentrum Karlsruhe GmbH, Institut für Technische Chemie (DE);MÜLLICH U, Forschungszentrum Karlsruhe GmbH, Institut für Technische Chemie (DE);MULLICH U, Forschungszentrum Karlsruhe GmbH, Institut fur Technische Chemie (DE)
Bibliographic Reference: EUR 16958 EN (1996) 73pp., FS, ECU 10
Availability: Available from the (2)
ISBN: ISBN 92-827-7987-4
Record Number: 199611336 / Last updated on: 1996-11-11
Original language: en
Available languages: en
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