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

N. D. Betenekov; A. V. Voronina; E. I. Denisov; M. L. Zelenskaya; E. S. Kudymov; E. V. Nogovitsina; N. N. Chopko

Vol 166

Pages:

169-171

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Research article

Radioactive waste and irradiated nuclear fuel management

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.

Бетенеков Н.Д., Воронина А.В., Денисов Е.И., Зеленская М.Л., Кудымов Е.С., Ноговицина Е.В., Чопко Н.Н. Разработка технологий изготовления сорбентов для выделения радионуклидов из отработанного ядерного топлива и методов радиохимического анализа и дезактивации жидких радиоактивных отходов // Записки Горного института. 2005. Т. 166. С. 169-171.

Betenekov N.D., Voronina A.V., Denisov E.I., Zelenskaya M.L., Kudymov E.S., Nogovitsina E.V., Chopko N.N. 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 // Journal of Mining Institute. 2005. Vol. 166. p. 169-171.

References

Бетенеков Н.Д. Применение модифицированных алюмосиликатов для очистки радиоактивно-загрязненных вод / Н.Д.Бетенеков, А.В.Воронина, Е.С.Кудымов // Вестник УГТУ-УПИ. Екатеринбург, 2004. № 5 (35). Ч.1.
Бетенеков Н.Д. Исследование механизма сорбции молибдена гидратированным оксидом титана / Н.Д.Бетенеков, Е.И.Денисов, Л.М.Шарыгин // Вестник УГТУ-УПИ. Екатеринбург, 2004. № 17 (47).
Денисов Е.И. Синтез селективных к йоду сорбентов и разработка способов для его извлечения из водных сред / Е.И.Денисов, М.Л.Зеленская //Вестник УГТУ-УПИ. Екатеринбург, 2004. № 5 (35). Ч.1.
Синтез и изучение свойств модифицированных сорбентов марки «Термоксид» / Н.Д.Бетенеков, А.В.Воронина, Н.Н.Чопко, Е.В.Ноговицына, Т.А.Недобух, Л.М.Шарыгин // Вестник УГТУ-УПИ. Екатеринбург, 2004. № 17 (47).

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

Abstract

References

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