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Vol 67, No 2 (2025)

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Articles

Uranium, thorium, and REE behavior in oxalate and oxalate-formate media

Kornilov А.S., Dmitrieva O.S., Vasyunina Е.V., Kopaneva K.O., Zamaltdinova A.R., Pozigun N.O., Boldakov V.А., Poglyad S.S.

Abstract

Thorium, uranium, and REE behavior in oxalic and oxalic–formate media was investigated. Thorium oxalate solubility in ammonium formate was determined. Some advice for uranium separation from thorium and REE was made. It is preferred to precipitate REE oxalates and to precipitate thorium oxalate with a non-isotopic carrier.

Radiohimiâ. 2025;67(2):103-111
pages 103-111 views

Recovery of protactinium from irradiated thorium nitrate by solvent extraction

Khokhlov M.L., Yakushin A.P., Fedorov Y.S., Samonin V.V., Davidenko V.D., Kovalishin A.A., Pavlov K.V., Titarenko Y.E., Kirsanov A.S., Arkhipov A.A., Kotel’nyi M.V.

Abstract

Recovery of protactinium from irradiated thorium nitrate by solvent extraction is studied in relation to the blanket conditions of a fusion neutron source (FNS) using n-octanol and diisobutylcarbinol (DIBC) as extractants. The degree of extraction of 233Pa from a solution of irradiated thorium nitrate (600 g/dm3) in 3 M nitric acid in one contact exceeded 80%, and the separation coefficients from uranium and thorium were obtained to be more than 600 and 130 000, respectively. To minimize the content of 232U in 233U (to less than 5 ppm), a procedure is proposed that includes short-term irradiation of thorium nitrate and continuous extraction of protactinium.

Radiohimiâ. 2025;67(2):112-118
pages 112-118 views

Cesium-137 extraction from nitric acid media with calix[4]arene-crown-6 ether solutions in bis(tetrafluoropropyl) carbonate

Aleksandrov T.S., Babitova E.S., Blokhin A.N., Brechalov A.А., Eremin V.V., Ermolenko Y.E., Karavan M.D., Kenf E.V., Maltseva T.V., Ostras' A.S., Timoshenko V.V., Tkachenko L.I., Smirnov I.V.

Abstract

The physicochemical and extraction properties of calixarene crown ethers: 1,3-alt-bis(octyloxy)calix[4]arene-crown-6 (II) and its derivatives with o-phenylene (I), methylenepropoxy (IV) and methylene(2,2,3,3-tetrafluoropropoxy) (III) substituents in the crown ether ring, were studied. Solutions of compound II in bis(2,2,3,3-tetrafluoropropyl) carbonate (BK-1) effectively extract cesium from 3 mol/L nitric acid already at a concentration of 0.001 mol/L. The introduction of substituents into the crown ether ring significantly reduces the efficiency of cesium extraction, but increases the solubility of calixarene crown ethers in bis(2,2,3,3-tetrafluoropropyl) carbonate. The data on the solubility of calixarene crown ethers in water and 3 mol/L nitric acid, the distribution between the organic and aqueous phases, and the rate of interaction with nitric acid were obtained. Calixarene crown ether I with an o-phenylene substituent reacts with 3 mol/L nitric acid approximately 2 times faster than dibenzo-21-crown-7. The other calixarene crown ethers studied do not react with nitric acid under the similar conditions. Quantum chemical modeling, including optimization of the structure geometry and calculation of vibrational frequencies, was performed for the molecules of calixarene crown ethers, DB21C7 and their complexes with the cesium cation. The calculated ΔG0 values for the complexation of ligands with the cesium cation correlate well with the experimental lgDCs (except for compound III with a fluorinated substituent). Solutions of calixarene crown ethers in bis(2,2,3,3-tetrafluoropropyl) carbonate exhibit selectivity for cesium and do not extract 152Eu and 241Am from nitric acid media.

Radiohimiâ. 2025;67(2):119-134
pages 119-134 views

Kinetic relationships of 90Sr sorption from aqueous solutions by carbonate-containing zirconium hydroxide Termoxid-3K

Belokonova N.V., Voronina A.V.

Abstract

The kinetic relationships of the 90Sr sorption from fresh water by Termoxid-3K inorganic sorbent were studied. The influence of the solution stirring rate, strontium concentration, and temperature on the sorption rate constant, diffusion coefficients, and kinetic regime was investigated, and the experimental results obtained were modeled using models of diffusion and chemical kinetics. The strontium sorption onto T-3K sorbent has a two-stage character and proceeds in the internal diffusion mode with a limiting contribution of the chemisorption process in the first stage. The diffusion coefficients of strontium were 10–12–10–13 m2/s, and the activation energy in the first stage of sorption was 93.3 and at the second stage, 23.8 kJ/mol.

Radiohimiâ. 2025;67(2):135-142
pages 135-142 views

Interference of strontium and yttrium cations and surfactants in competitive adsorption onto activated carbon: a radioatracer study

Chernysheva M.G., Kangina O.A., Spivak Е.Y., Gopin A.V., Badun G.A.

Abstract

The interference of Sr(II) and Y(III) cations with cationic, anionic, and nonionic surfactants during competitive adsorption on lignin-produced activated carbon was studied. Dodecyltrimethylammonium bromide, sodium dodecylsulfate, and decaethylene glycol monododecyl ether (Brij-35) were used as surfactants. The radiotracers 90Sr/90Y and tritium were used to trace the equilibrium concentration of metal cations and the surface concentrations of the surfactants, respectively. Tritium-labeled surfactants were obtained using the tritium thermal activation technique. Liquid scintillation spectrometry was used to determine the concentration of all substances. The SpectraDec software was used for joint measurement of 90Sr/90Y and tritium radioactivity. It was shown that the presence of a surfactant affects the adsorption of strontium and yttrium onto activated carbon produced by thermochemical activation with orthophosphoric acid. The formation of a low-solubility precipitate with an anionic surfactant increased the adsorption of both cations, reduced their desorption, and promoted the sorption of the anionic surfactant itself. The nonionic surfactant (containing oxyethyl groups) did not affect the adsorption of strontium and yttrium cations but helped retain them on the carbon surface, preventing desorption. The cationic surfactant competed with strontium and yttrium cations for active sites on the activated carbon surface: adsorption of all components decreased, while desorption of cations increased.

Radiohimiâ. 2025;67(2):143-149
pages 143-149 views

Sorption of americium by detonation synthesis nanodiamonds from aqueous solutions of various compositions

Kazakov А.G., Pavlova D.V., Vinokurov S.E., Myasoedov B.F.

Abstract

Sorption of americium by commercial samples of detonation nanodiamonds (NDs) from nitric acid, neutral, and alkaline solutions was investigated. Sorption kinetics and dependence of sorption degree on pH, ionic strength, m/V ratio and temperature were studied. Thermodynamic parameters of americium adsorption by NDs were determined for the first time. Conditions of quantitative sorption of americium by NDs samples were found; it was shown that NDs are promising sorbents for decontamination of natural waters from possible americium impurities.

Radiohimiâ. 2025;67(2):150-157
pages 150-157 views

1,2-diformylhydrazine oxidation with nitric acid

Dvoeglazov K.N., Arkhipova M.A., Ambartsumyan A.А.

Abstract

The kinetics of 1,2-diformylhydrazine (reagent suggested for the reductive stripping of plutonium in the Purex process) oxidation with nitric acid was studied. The rate equation is first-order with respect to the reductant and third-order with respect to nitric acid in the interval [HNO3] = 5.5–9.0 mol/L. It is postulated that reaction between diformylhydrazine and nitric acid involves their molecular undissociated forms. The activation energy of the reaction is 116 kJ/mol in temperature range 70–90°С.

Radiohimiâ. 2025;67(2):158-164
pages 158-164 views

Characterization of particles formed during laser cutting of simulated fuel-containing materials from the Fukushima-Daiichi NPP and of SNF samples

Makarov А.O., Momotov V.N., Semin S.D., Nikitin O.N., Lakeev P.V., Efimov V.A., Reztsova V.А., Tikhonova D.E.

Abstract

Fragmentation of massive debris of the fuel and fuel-containing materials (FCMs) is one of important steps in the final decommissioning of the Fukushima Daiichi NPP. The generation and dissemination of radioactive microparticles in the course of the fragmentation largely depend on the cutting technology used. A previous study [1] dealt with the experimental cutting of simulated FCM and spent nuclear fuel (SNF) samples to justify the optimum configuration and operation conditions of the gas treatment system. To understand the properties of particles generated in the course of cutting FCM and SNF samples and to justify the methods for their localization, it is necessary to study in more detail the size, shape, and composition of the structures formed. We used in this study the microparticles formed by laser cutting of simulated FCMs from the Fukushima Daiichi NPP and of SNF samples. The microparticles formed were examined with a laser particle size analyzer and with a scanning electron microscope equipped with wave- and energy-dispersive spectrometers. The formation of particles of different size and morphology was noted. The laser cutting generates separate particles of submicron size and different morphology, which form agglomerates. Up to 35 wt % of particles formed by laser cutting of the simulated FDM passed into the vapor–gas phase. For the VVER (water-cooled water-moderated energy reactor) SNF, this fraction was 25 wt %. The major components of all kinds of particles formed by laser cutting of SNF are uranium, oxygen, and zirconium; their total fraction is in the range from 97.9 to 98.4%. The plutonium content ranges from 0.7 to 1.3%.

Radiohimiâ. 2025;67(2):165-175
pages 165-175 views

Discharge of 137Cs from Lake Saimaa into the Vuoksa River and Lake Ladoga

Bakunov N.А., Bolshiyanov D.Y., Pravkin S.А., Aksenov A.O.

Abstract

The migration of 137Cs from the upper reaches of the Vuoksa River, Lake Saimaa, to Lake Ladoga was studied to determine the role of the river in the contamination of Lake Ladoga with 137Cs from the Chernobyl accident. During the migration period from 1988 to 2024, the concentration of 137Cs in the river water decreased from 113 to approximately 4.0 Bq/m³. By 2015, the 137Cs content in the Vuoksa River had approached the pre-accident level of 4–5 Bq/m³, which was due to global 137Cs contamination of river waters. The decrease in “Chernobyl” 137Cs in the Vuoksa River was approximated by a two-component exponential dependence with the water purification half-lives of T1 = 5 and T2 = 25 years, respectively. The discharge of “Chernobyl” 137Cs with Vuoksa’s waters from Finnish Lake Saimaa in 1986–2023 amounted to 22.5 TBq – a value roughly comparable to the deposition of “Chernobyl” 137Cs (74.1 TBq) on Lake Ladoga in 1986. During 1986–1988, the discharge of “Chernobyl” 137Cs from Lake Saimaa amounted to approximately 30% of the total for 1986–2024. The long-term transit of 137Cs from Lake Saimaa has led to increased accumulation of 137Cs (≈300 Bq/kg) in the sediment profile of the Vuoksa River and the lakes within its basin.

Radiohimiâ. 2025;67(2):176-181
pages 176-181 views