The solvent extraction of Am(VI) using centrifugal contactors
One of the major challenges in nuclear fuel cycle research is the development of a separation that can be deployed on a process scale for americium from the lanthanides. Unlike most lanthanides, americium can be oxidized to higher oxidation states, and this presents an opportunity to exploit high valent americium for such a separation. Strong oxidizing agents are required. However, the preparation of hexavalent americium using sodium bismuthate has now become routine in our laboratory. The success of separations based on oxidized americium depends on not only the yield of the higher oxidation state, but also its persistence in solution. In batch contact work, short contact times allowed for the extraction of Am(VI) with DAm ~ 4, using 1 M diamylamylphosphonate as the ligand. Based on bench-scale extraction and stripping studies a flowsheet was designed and a hot test was performed in a radiological fume hood using three CINC, 5-cm centrifugal contactors. Stage 1 was the americium extraction stage. In stage 2, americium stripping was attempted after reduction with a low concentration of hydrogen peroxide. As the only lanthanide that oxidizies and extracts in this flowsheet, it was attempted to reduce and strip cerium in the third stage contactor. The results of this hot test are compared with batch extraction studies, where it was found that americium extraction was comparable to batch contacts, while stripping was less efficient than expected. Proposals for the next test are discussed.
- Research Organization:
- Idaho National Laboratory, Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1372832
- Report Number(s):
- INL/CON-14-33658
- Country of Publication:
- United States
- Language:
- English
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