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Actinides and fission products in reactor graphite after loss-of-flow accidentстатья
Информация о цитировании статьи получена из
Scopus,
Web of Science
Статья опубликована в журнале из списка Web of Science и/или Scopus
Дата последнего поиска статьи во внешних источниках: 11 мая 2022 г.
- Авторы: Pavlyuk Alexander O., Kotlyarevskii Sergei G., Kan Roman I., Volkova Anna G., Yapaskurt Vasiliy O., Zakharova Elena V., Shiryaev Andrei A.
- Журнал: npj Materials Degradation
- Том: 6
- Номер: 1
- Год издания: 2022
- Издательство: Springer Nature
- Местоположение издательства: Switzerland
- Номер статьи: 23
- DOI: 10.1038/s41529-022-00235-3
- Аннотация: Samples of irradiated graphite from a uranium-graphite reactor contaminated with fuel debris from loss-of-flow accidents, are investigated. Peculiarities of spatial distribution, speciation, and kinetics of leaching by aqueous solution of actinides and fissionproducts are studied at scales from the whole reactor stack down to sub-mm graphite fragments. The main fraction of fuel debris isassociated with aluminosilicate-based phases decorating cracks and other defects of damaged graphite details. Elemental composition of actinides and fission products depends on both irradiation and leaching conditions. Significant differences are observed between leach kinetics of various radionuclides; integral leached fraction varies between ~5% for 244Сm to ~90% for 134,137Cs. For some radionuclides sudden massive release due to uneven dissolution of the carrier phases is observed. Disposal of irradiated graphite with significant fraction of fuel debris requires dedicated treatment aimed either at decontamination or at conversion of the radionuclides to insoluble well-fixed form.
- Добавил в систему: Ширяев Андрей Альбертович