The paper describes the use of a promising sorbent T-52 for Mo-99 extraction from LEU fuel of a homogeneous solution reactor. T-52 is characterized as having maximal Mo-99 distribution coefficient in the course of Mo-99 sorption from strong uranium solutions with concentration of more than 200 g/l. Adoption of sulfate and nitrate solutions for Mo-99 production and extraction from irradiated fuel of homogeneous solution reactor was studied by means of comparative analysis. The optimal (in terms of chemical technology) conditions of molybdenum separation from LEU fuel solution are proposed. The paper emphasizes the importance of an integrated approach while designing a homogeneous solution reactor as well as developing the Mo-99 separation method.
Translated title of the contributionDevelopment of a Method for Extraction of Mo-99 from Low Enriched Uranium Fuel of Homogeneous Solution Reactor
Original languageRussian
Pages (from-to)56-65
Number of pages10
JournalВопросы радиационной безопасности
Issue number4(80)
Publication statusPublished - 2015

    GRNTI

  • 31.17.00

    Level of Research Output

  • VAK List

ID: 1902143