Abstract

An Actinide Lanthanide Separation Process (ALSEP) for the separation of trivalent actinides (An(III)) from simulated raffinate solution was successfully demonstrated using a 32-stage 1 cm annular centrifugal contactor setup. The ALSEP solvent was composed of a mixture of 2-ethylhexylphosphonic acid mono-2-ethylhexyl ester (HEH[EHP]) and N,N,N′,N′-tetra-(2-ethylhexyl)-diglycolamide (T2EHDGA) in n-dodecane. Flowsheet calculations and evaluation of the results were done using the Argonne’s Model for Universal Solvent Extraction (AMUSE) code using single-stage distribution data. The co-extraction of Zr(IV) and Pd(II) was prevented using CDTA (trans-1,2-diaminocyclohexane-N,N,N′,N′-tetraacetic acid) as a masking agent in the feed. For the scrubbing of co-extracted Mo; citrate-buffered acetohydroxamic acid was used. The separation of An(III) from the trivalent lanthanides (Ln(III)) was achieved using citrate-buffered diethylene-triamine-N,N,N′,N″,N″-pentaacetic acid (DTPA), and Ln(III) were efficiently back extracted using N,N,N′,N′-tetraethyl-diglycolamide (TEDGA). A clean An(III) product was obtained with a recovery of 95% americium and curium. The Ln(III) were efficiently stripped; but the Ln(III) product contained 5% of the co-stripped An(III). The carryover of Am and Cm into the Ln(III) product is attributed to too few actinide stripping stages, which was constrained by the number of centrifugal contactors available. Improved separation would be achieved by increasing the number of An strip stages. The heavier lanthanides (Pr, Nd, Sm, Eu, and Gd) and yttrium were mainly routed to the Ln product, whereas the lighter lanthanides (La and Ce) were mostly routed to the raffinate.

Highlights

  • Different waste management strategies for the handling of irradiated used nuclear fuel from nuclear power plants are followed worldwide by different countries [1]

  • French studies showed that the separation of minor actinides (MA: Np, Am, and Cm), especially Am, would reduce the total repository volume by up to a factor of seven [6,7,8]

  • A synthetic Actinide Lanthanide Separation Process (ALSEP) feed simulant was prepared with a target composition that would be expected for the raffinate from a U/Pu co-decontamination process [31]

Read more

Summary

Introduction

Different waste management strategies for the handling of irradiated used nuclear fuel from nuclear power plants are followed worldwide by different countries [1]. While several countries (e.g., Germany and the United States) follow a direct disposal strategy (i.e., no further treatment of irradiated used nuclear fuel), other countries (e.g., France) follow a recycling strategy for U and. Waste will need to be disposed of in an underground repository. Such underground repositories are extremely rare with only a handful of repositories in operation worldwide (e.g., the Waste Isolation Pilot Plant (WIPP) in the United States for the disposal of defense waste), and a few sites under investigation or in the licensing process. French studies showed that the separation of minor actinides (MA: Np, Am, and Cm), especially Am, would reduce the total repository volume by up to a factor of seven [6,7,8]

Methods
Results
Conclusion
Full Text
Paper version not known

Talk to us

Join us for a 30 min session where you can share your feedback and ask us any queries you have

Schedule a call