Separation and purification of elements from alkaline and carbonate nuclear waste solutions

Alexander V. Boyarintsev; Sergei I. Stepanov; Galina V. Kostikova; Valeriy I. Zhilov; Alfiya M. Safiulina; Aslan Yu Tsivadze

Nuclear Engineering and Technology (Feb 2023)

Separation and purification of elements from alkaline and carbonate nuclear waste solutions

Alexander V. Boyarintsev,
Sergei I. Stepanov,
Galina V. Kostikova,
Valeriy I. Zhilov,
Alfiya M. Safiulina,
Aslan Yu Tsivadze

Affiliations

Alexander V. Boyarintsev: Mendeleev University of Chemical Technology, Miusskaya Square 9, 125047, Moscow, Russian Federation; A.N. Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences, Leninsky Prospect 31/4, Moscow, 119071, Russian Federation; Corresponding author. Mendeleev University of Сhemical Technology, Department of Technology of Rare Elements and Nanomaterials based on them, 125047, Miusskaya square, 9, Moscow, Russian Federation.
Sergei I. Stepanov: Mendeleev University of Chemical Technology, Miusskaya Square 9, 125047, Moscow, Russian Federation; A.N. Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences, Leninsky Prospect 31/4, Moscow, 119071, Russian Federation
Galina V. Kostikova: A.N. Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences, Leninsky Prospect 31/4, Moscow, 119071, Russian Federation
Valeriy I. Zhilov: A.N. Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences, Leninsky Prospect 31/4, Moscow, 119071, Russian Federation
Alfiya M. Safiulina: JSC Academician A.A. Bochvar High-Tech Research Institute of Inorganic Materials, Rogova Street 5a, Moscow, 123060, Russian Federation
Aslan Yu Tsivadze: A.N. Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences, Leninsky Prospect 31/4, Moscow, 119071, Russian Federation

Journal volume & issue: Vol. 55, no. 2
pp. 391 – 407

Abstract

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This article provides a survey of wet (aqueous) methods for recovery, separation, and purification of uranium from fission products in carbonate solutions during the reprocessing of spent nuclear fuel and methods for removal of radionuclides from alkaline radioactive waste. The main methods such as selective direct precipitation, ion exchange, and solvent extraction are considered. These methods were compared and evaluated for reprocessing of spent nuclear fuel in carbonate media according to novel alternative non-acidic methods and for treatment processes of alkaline radioactive waste.

Published in Nuclear Engineering and Technology

ISSN: 1738-5733 (Print)
Publisher: Elsevier
Country of publisher: Korea, Republic of
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: http://www.journals.elsevier.com/nuclear-engineering-and-technology

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