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Solvent extraction systems for mutual separation of Am(III) and Cm(III) from nitric acid solutions. A review of recent state-of-the-artстатья
- Авторы: Matveev Petr I., Mohapatra Prasanta K., Kalmykov Stepan N., Petrov Vladimir G.
- Журнал: Solvent Extraction and Ion Exchange
- Том: 39
- Номер: 7
- Год издания: 2021
- Издательство: Taylor & Francis
- Местоположение издательства: United Kingdom
- Первая страница: 679
- Последняя страница: 713
- Номер статьи: 1
- DOI: 10.1080/07366299.2020.1856998
- Аннотация: Americium and curium, present in spent nuclear fuel, are carried forward to the high-level wastes (HLW) upon its reprocessing within the closed nuclear fuel cycle strategy. These minor actinides are required to be extracted efficiently to mitigate the long-term radiotoxicity of the HLW, which in some countries is the proposed strategy for the safe management of radioactive wastes emanating from the reprocessing of spent nuclear fuel. While both Am and Cm are co-extracted by most of extractants used for actinide partitioning and lanthanide-actinide separations, their mutual separation makes Am transmutation less complicated. In their most stable (trivalent) oxidation state, these elements are very difficult to separate. In this review, solvent extraction systems for the mutual separation of Am(III) and Cm(III) from nitric acid solutions are discussed. The extraction systems for the separation of americium directly from high-level liquid waste and from isolated mixtures of americium and curium are considered.
- Добавил в систему: Матвеев Петр Игоревич