Development of technologies for production of sorbents for radionuclide extraction from spent nuclear fuel and methods of radiochemical analysis and decontamination of liquid radioactive waste
Authors:
About authors
- 1 — Ural State Technical University
- 2 — Ural State Technical University
- 3 — Ural State Technical University
- 4 — Ural State Technical University
- 5 — Ural State Technical University
- 6 — Ural State Technical University
- 7 — Ural State Technical University
Abstract
New grades of inorganic sorbents based on natural materials and artificial materials (thermoxide sorbents) suitable for extraction of Cs-137 from liquid radioactive waste have been developed. The technology of selective extraction of Mo-99 from spent nuclear fuel for scientific and medical purposes using inorganic sorbents, previously developed by the Department of Radiochemistry of UGTU, has been optimized. Ag-sorbents based on thermoxide-5 carrier were developed and optimal conditions of I-131 extraction by these sorbents from aqueous solutions were determined. The technology of Mo-99 production was supplemented with a new stage of I-131 extraction from alkaline concentrate Mo-99 after desorption operation.
Область исследования:
(Archived) Radioactive waste and irradiated nuclear fuel management
Funding:
None
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