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Vol 166
Pages:
169-171
Download volume:
RUS
Article

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:
N. D. Betenekov1
A. V. Voronina2
E. I. Denisov3
M. L. Zelenskaya4
E. S. Kudymov5
E. V. Nogovitsina6
N. N. Chopko7
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
Date submitted:
2005-01-12
Date accepted:
2005-02-14
Date published:
2005-12-15

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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