2022 Annual Meeting

(268a) Development of Extraction Process Flowsheets for Recovery of Uranium from Used Nuclear Fuel

Authors

Candido Pereira - Presenter, Argonne National Laboratory
Laura Maggos, Argonne National Laboratory
Jackie Copple, Argonne National Laboratory
As part of recent efforts to develop solvent extraction systems for the treatment of spent nuclear fuel, the Argonne Model for Universal Solvent Extraction (AMUSE) was used to design flowsheets to enable recycle of uranium from spent oxide fuels. A complete abstract will be submitted.