Removal of Tritium from Gas Flows from Working Areas of Nuclear Facilities

M. B. Rozenkevich; Розенкевич М. Б.; N. N. Kulov; Кулов Н. Н.; Yu. S. Pak; Пак Ю. С.; A. N. Bukin; Букин А. Н.; V. S. Moseeva; Мосеева В. С.; S. A. Marunich; Марунич С. А.

doi:10.31857/S0040357123030156

Removal of Tritium from Gas Flows from Working Areas of Nuclear Facilities

Authors: Rozenkevich M.B.¹, Kulov N.N.², Pak Y.S.¹, Bukin A.N.¹, Moseeva V.S.¹, Marunich S.A.¹
Affiliations:
1. D. Mendeleev University of Chemical Technology of Russia
2. Kurnakov Institute of General and Inorganic Chemistry, Russian Academy of Sciences
Issue: Vol 57, No 3 (2023)
Pages: 257-265
Section: Articles
Published: 01.05.2023
URL: https://bakhtiniada.ru/0040-3571/article/view/138460
DOI: https://doi.org/10.31857/S0040357123030156
EDN: https://elibrary.ru/RPMBVY
ID: 138460

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Abstract

Some methods were considered to remove tritium-containing hydrogen compounds from various gas flows from scientific and production facilities in the nuclear and thermonuclear power industry. The possibilities of tritium removal from a gas flow in the form of hydrogen were analyzed, and it was concluded that these methods can be applied at low flow rates of the gas being purified. At high gas flow rates, the main detritiation methods are adsorption and water phase isotope exchange. Both these methods include the preliminary catalytic oxidation of tritium-containing molecules to water with the further removal of tritiated water from the gas. The main technological parameters of these methods were compared, and it was inferred that phase isotope exchange has great advantages.

Keywords

tritium, gas flows, methods of removal, hydrogen, water, adsorption, phase isotope exchang

References

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