Smaller Amides for More Efficient Uranium Extraction

Amide extractants are promising CHON-based alternatives to tri-n-butyl phosphate for uranium recovery in nuclear fuel reprocessing due to their combustibility and improved radiolytic stability. We report a systematic structure-performance evaluation of 16 amide extractants to define correlations between structure, uranium loading, solvent viscosity, aggregation behavior, and degradation product solubility. Amide molecular weight (213–325 g/mol) and steric environment were tuned through variation of N,N-alkyl substitution and α-carbon branching. Uranium extraction was assessed using a direct dissolution approach in nitric acid media in the presence of representative fission product surrogates. Several amides formed neutral [(amide)2UO2(NO3)2] complexes with uranium loadings up to 0.60 M while maintaining low solution viscosity and avoiding third‑phase formation. Structure-property correlations indicate that optimal performance requires moderate molecular weight (213–283 g/mol), asymmetric N,N-substitution with a combined alkyl-chain length of 13 carbons or fewer, and together with limited steric crowding at the carbonyl oxygen atom to strike a balance between coordination strength and aggregation. Three candidates met these criteria and exhibited improved viscosity and phase stability relative to leading amide extractants, providing design principles and molecular-level guidance for the design of next-generation amide extractants for uranium reprocessing applications.

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Publication Details

Journal
Solvent Extraction and Ion Exchange
Published
2026-10-13
DOI
https://doi.org/10.1080/07366299.2026.2741567
Primary Topic
Radioactive element chemistry and processing
Type
article
Field-Weighted Citation Impact
0.00

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article

Smaller Amides for More Efficient Uranium Extraction

Miles A. Lamb, Santa Jansone‐Popova, Jopaul Mathew, Jeffrey D. Einkauf
Solvent Extraction and Ion Exchange
Radioactive element chemistry and processing
article

Smaller Amides for More Efficient Uranium Extraction

Miles A. Lamb, Santa Jansone‐Popova, Jopaul Mathew, Jeffrey D. Einkauf
article en

Abstract

Amide extractants are promising CHON-based alternatives to tri-n-butyl phosphate for uranium recovery in nuclear fuel reprocessing due to their combustibility and improved radiolytic stability. We report a systematic structure-performance evaluation of 16 amide extractants to define correlations between structure, uranium loading, solvent viscosity, aggregation behavior, and degradation product solubility. Amide molecular weight (213–325 g/mol) and steric environment were tuned through variation of N,N-alkyl substitution and α-carbon branching. Uranium extraction was assessed using a direct dissolution approach in nitric acid media in the presence of representative fission product surrogates. Several amides formed neutral [(amide)2UO2(NO3)2] complexes with uranium loadings up to 0.60 M while maintaining low solution viscosity and avoiding third‑phase formation. Structure-property correlations indicate that optimal performance requires moderate molecular weight (213–283 g/mol), asymmetric N,N-substitution with a combined alkyl-chain length of 13 carbons or fewer, and together with limited steric crowding at the carbonyl oxygen atom to strike a balance between coordination strength and aggregation. Three candidates met these criteria and exhibited improved viscosity and phase stability relative to leading amide extractants, providing design principles and molecular-level guidance for the design of next-generation amide extractants for uranium reprocessing applications.

Solvent Extraction and Ion Exchange
Oak Ridge National Laboratory (US)
U.S. Department of Energy, Oak Ridge National Laboratory
Openalex Percentile: Top 28%
Radioactive element chemistry and processing
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