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Technical and Methodological Support for Studies of Radioactive Graphite-containing Slurries in Technological Containersстатья
- Авторы: Pavlyuk A.O., Kotlyarevsky S.G., Zaderyaka A.A., Kuzov V.A., Shevchenko O.M., Zakharova E.V., Volkova A.G.
- Журнал: Radiochemistry
- Том: 64
- Номер: 6
- Год издания: 2022
- Издательство: Pleiades Publishing, Inc.
- Местоположение издательства: New York, USA
- Первая страница: 747
- Последняя страница: 753
- Оригинальные версии: Технологическое и методическое обеспечение исследований радиоактивных графитсодержащих пульп в технологических емкостях
- Аннотация: The article refl ects the problem of graphite-containing slurries accumulated, as deposit, in technological systems during the operation of uranium-graphite reactors. Technical and methodological approaches to the performance of work on the survey of containers are presented, which made it possible to remotely select highly active samples of graphite-containing slurry from closed containers located in radiation-hazardous rooms, and to estimate the volume, layer thickness, and surface profi le of deposits. Methods are described, including radiochemical ones, used in the course of research to determine the radionuclide composition, activity levels, amounts of solid and liquid phases, moisture content, and mass loss on ignition. To predict the behavior of radionuclides sorbed on deposits, the selective desorption method was used to determine the water-soluble, ion-exchange, low-mobility, strongly bound, and strongly fi xed forms of radionuclides in samples of graphite-containing slurry. The results obtained were used to assess nuclear and radiation safety, as well as to develop technological methods for handling graphite-containing slurries during the decommissioning of containers. Proven approaches to survey and laboratory analysis of deposits can be used in the inspection of other similar containers containing high-level deposits.
- Добавил в систему: Волкова Анна Генриховна