(486b) Extraction Model Development and Enhancements for the Amuse Code

Recent interest in developing simplified solvent extraction processes for recycle of high-assay low-enriched uranium (HALEU) has motivated the expansion of solvent extraction modeling capabilities in the Argonne Model for Universal Solvent Extraction (AMUSE). The monoamide extractant N,N-di-2-ethylhexyl-isobutyramide (DEHiBA) is under study for the selective separation of uranium from the transuranic elements and the other irradiated nuclear fuel components. Distribution ratio (D value) models for key nuclear fuel components (including U, Np, Pu, Am, Tc, and Zr) are being developed for solvent extraction with DEHiBA in AMUSE to support development of uranium extraction flowsheets. The updated AMUSE code has been used to design spent fuel treatment flowsheets that use DEHiBA as the extractant. Additional capabilities added to AMUSE to improve performance and applicability to different processes will also be described.

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