A highly efficient extraction system for Am(iii)–Cm(iii) pair separation in spent nuclear fuel reprocessing

Abstract

Closing the nuclear fuel cycle is a key objective in the development of Generation IV nuclear systems, enabling the recycling of actinides and reducing the long-term radiotoxicity of nuclear waste. Americium is a prime candidate for transmutation, but its effective use requires high-purity separation from chemically similar curium and lanthanides. In this work, we report the design, synthesis, and evaluation of a novel extractant, 4,7-dicyano-N,N′-diethyl-N,N′-diphenyl-1,10-phenanthroline-2,9-dicarboxamide (DAPhenCN), for selective separation of Am(III) from Cm(III). This extractant was selected for synthesis based on the DFT modeling results of the complexes of 4- and 7-disubstituted 1,10-phenanthroline-2,9-dicarboxamides with Am(III), Cm(III) and lanthanides(III). Solvent extraction experiments revealed Am/Cm separation factors (SFAm/Cm) of 5–6, with favorable distribution ratios for counter-current processing. Crucially, DAPhenCN demonstrated excellent resistance to hydrolysis and radiolysis under α-, γ-, and electron-beam irradiation. Counter-current tests using real raffinates from VVER-1000 spent nuclear fuel reprocessing confirmed the robustness and efficiency of the extraction system, achieving >99% americium recovery and >99.9% curium purity. Light lanthanides partially co-extracted with Am(III), while heavier ones had no significant impact. The developed process enables the production of curium-free americium suitable for transmutation fuel fabrication, advancing the implementation of closed nuclear fuel cycles.

Graphical abstract: A highly efficient extraction system for Am(iii)–Cm(iii) pair separation in spent nuclear fuel reprocessing

Supplementary files

Article information

Article type
Research Article
Submitted
23 Jul 2025
Accepted
18 Oct 2025
First published
21 Oct 2025

Inorg. Chem. Front., 2026, Advance Article

A highly efficient extraction system for Am(III)–Cm(III) pair separation in spent nuclear fuel reprocessing

V. G. Petrov, P. I. Matveev, V. G. Nenajdenko, Yu. A. Ustynyuk, I. P. Gloriozov, M. V. Evsiunina, P. S. Lemport, N. A. Avagyan, V. S. Petrov, A. D. Krot, P. Kalle, V. N. Khrustalev, N. D. Goletskiy, A. A. Naumov and S. N. Kalmykov, Inorg. Chem. Front., 2026, Advance Article , DOI: 10.1039/D5QI01560J

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