A highly efficient extraction system for Am( iii )–Cm( iii ) pair separation in spent nuclear fuel reprocessing Научная публикация
| Журнал |
Inorganic Chemistry Frontiers
ISSN: 2052-1553 , E-ISSN: 2052-1545 |
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| Вых. Данные | Год: 2026, Том: 13, Страницы: 555-563 Страниц : 9 DOI: 10.1039/d5qi01560j | ||||||||||
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| Организации |
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Информация о финансировании (1)
| 1 | Институт органической химии им. Н. Д. Зелинского Российской академии наук |
Реферат:
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.
Библиографическая ссылка:
Petrov V.G.
, Matveev P.I.
, Nenajdenko V.G.
, Ustynyuk Y.A.
, Gloriozov I.P.
, Evsiunina M.V.
, Lemport P.S.
, Avagyan N.A.
, Petrov V.S.
, Krot A.D.
, Kalle P.
, Khrustalev V.N.
, Goletskiy N.D.
, Naumov A.A.
, Kalmykov S.N.
A highly efficient extraction system for Am( iii )–Cm( iii ) pair separation in spent nuclear fuel reprocessing
Inorganic Chemistry Frontiers. 2026. V.13. P.555-563. DOI: 10.1039/d5qi01560j WOS Scopus OpenAlex
A highly efficient extraction system for Am( iii )–Cm( iii ) pair separation in spent nuclear fuel reprocessing
Inorganic Chemistry Frontiers. 2026. V.13. P.555-563. DOI: 10.1039/d5qi01560j WOS Scopus OpenAlex
Идентификаторы БД:
| Web of science: | WOS:001609451000001 |
| Scopus: | 2-s2.0-105027728682 |
| OpenAlex: | W4415403598 |
Цитирование в БД:
| БД | Цитирований |
|---|---|
| OpenAlex | Нет цитирований |
| Scopus | Нет цитирований |