Purification of U from U-10Mo scrap generated during the fabrication of high performance research reactor fuel

A low enriched U-Mo alloy fuel is under development to replace highly enriched U fuels currently used in United States high performance research reactors. The alloy casting and fuel fabrication processes will generate scrap streams containing low enriched U (LEU) which must be recovered. Solvent extraction processes were designed using the Argonne Model for Universal Solvent Extraction (AMUSE) to purify solutions containing 20 and 50 g/L U. The feed for the solvent extraction processes was prepared from solutions generated from the dissolution of U-10Mo-Zr foils and U-10Mo-Zr-Al mini-plates. The U purification processes were demonstrated using two, 16-stage banks of miniature mixer-settlers. The solvent extraction experiments demonstrated that all design objectives for the U purification processes could be met. The U recovery in the product stream for each flowsheet was ≥99.9%. The flowsheet demonstrations also showed that the purity of the U Product will meet the requirements of the ASTM International C1462-21 specification for LEU metal enriched to less than 20% <sup>235</sup>U. In conclusion, the AMUSE modeling for both flowsheet demonstrations was validated by comparing predicted and measured concentrations of U, Mo, and Zr in the exit streams and stage samples at steady-state conditions in the mixer-settlers.

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Publication Details

Journal
Separation Science and Technology
Published
2024-11-28
DOI
https://doi.org/10.1080/01496395.2024.2428357
Primary Topic
Nuclear Materials and Properties
Type
article
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Purification of U from U-10Mo scrap generated during the fabrication of high performance research reactor fuel

Tracy S. Rudisill, Candido Pereira
Separation Science and Technology
Nuclear Materials and Properties
article

Purification of U from U-10Mo scrap generated during the fabrication of high performance research reactor fuel

Tracy S. Rudisill, Candido Pereira
article en

Abstract

A low enriched U-Mo alloy fuel is under development to replace highly enriched U fuels currently used in United States high performance research reactors. The alloy casting and fuel fabrication processes will generate scrap streams containing low enriched U (LEU) which must be recovered. Solvent extraction processes were designed using the Argonne Model for Universal Solvent Extraction (AMUSE) to purify solutions containing 20 and 50 g/L U. The feed for the solvent extraction processes was prepared from solutions generated from the dissolution of U-10Mo-Zr foils and U-10Mo-Zr-Al mini-plates. The U purification processes were demonstrated using two, 16-stage banks of miniature mixer-settlers. The solvent extraction experiments demonstrated that all design objectives for the U purification processes could be met. The U recovery in the product stream for each flowsheet was ≥99.9%. The flowsheet demonstrations also showed that the purity of the U Product will meet the requirements of the ASTM International C1462-21 specification for LEU metal enriched to less than 20% <sup>235</sup>U. In conclusion, the AMUSE modeling for both flowsheet demonstrations was validated by comparing predicted and measured concentrations of U, Mo, and Zr in the exit streams and stage samples at steady-state conditions in the mixer-settlers.

Separation Science and TechnologyVol. 61(3-5)
Argonne National Laboratory (US), Savannah River National Laboratory (US)
Openalex Percentile: Top 86%
Nuclear Materials and Properties
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Purification of U from U-10Mo scrap generated during the fabrication of high performance research reactor fuel — Tracy S. Rudisill, Candido Pereira · Separation Science and Technology (2024) | TGRS Research Map | TGRS