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Vol 59, No 2 (2017)

Article

Possibility of using hydrogen peroxide for trapping nitrogen oxide at radiochemical enterprises

Ustinov O.A., Yakunin S.A.

Abstract

Published data on the reaction of H2O2 with nitrogen oxides and HNO2 were analyzed and summarized as applied to the problems of trapping nitrogen oxides from off-gases. H2O2 reacts only with NO and HNO2 dissolved in aqueous solution, and the NO solubility increases with increasing HNO3 concentration. Examples of enhancing the efficiency of trapping nitrogen oxides by using Н2О2 are presented.

Radiochemistry. 2017;59(2):109-112
pages 109-112 views

Synthesis and X-ray diffraction study of uranyl malonate monohydrate

Medvedkov Y.A., Grigor’ev M.S., Serezhkina L.B., Rogalev E.F., Pushkin D.V., Serezhkin V.N.

Abstract

Uranyl malonate monohydrate [UO2(mal)(H2O)], where mal2– is malonate ion, was synthesized and studied by single crystal X-ray diffraction. The main structural units are electrically neutral [UO2(mal)(H2O)] layers belonging to crystal-chemical group AQ21М1 (A = UO22+, Q21 = mal2–, M1 = H2O) of uranyl complexes. Specific features of the packing of the uranium-containing complexes are discussed on the basis of Voronoi–Dirichlet tessellation. The structural differences between the monohydrate synthesized and the known uranyl malonate trihydrate are considered.

Radiochemistry. 2017;59(2):113-118
pages 113-118 views

Synthesis, crystal structure, and properties of new actinide(VI) arsenates (H3O)[(AnO2)(AsO4)]·3H2O (An = U, Np, Pu)

Ivanova A.G., Budantseva N.A., Fedoseev A.M.

Abstract

Previously unknown arsenates of hexavalent U, Np, and Pu, (H3O)[(UO2)(AsO4)]·3H2O (I), (H3O)· [(NpO2)(AsO4)]·3H2O (II), and (H3O)[(PuO2)(AsO4)]·3H2O (III), were synthesized under hydrothermal conditions. The crystal structure of the compounds was determined, and their absorption spectra were measured. The compounds crystallize in tetragonal space group P4/nmm.

Radiochemistry. 2017;59(2):119-123
pages 119-123 views

New data on Np(VII) compounds with Co(NH3)63+. Crystal structure of [Co(NH3)6]3[NpO4(OH)2]3·4H2O and refinement of the structure of [Co(NH3)6][NpO4(OH)2]·2H2O

Charushnikova I.A., Krot N.N., Grigor’ev M.S., Makarenkov V.I.

Abstract

The structure and properties of the needle-like phase of crystalline compounds of the general composition Co(NH3)6NpO5·nH2O, precipitated from alkaline Np(VII) solutions with [Co(NH3)6]3+ ions, were studied. The needle-like phase under the layer of the mother liquor is unstable and transforms into a platelike phase identified as [Co(NH3)6][NpO4(OH)2]·2H2O (1). In the structure of 1, all the Np atoms are equivalent, but the Mössbauer spectrum recorded at a liquid helium temperature revealed the presence of two nonequivalent Np atoms. The isolated needle-like phase, according to single crystal X-ray diffraction data, at 100 K has the composition [Co(NH3)6]3[NpO4(OH)2]3·4H2O (2). In the structure of 2, there are two crystallographically independent Np(VII) atoms. The Np(1) atom is in the inversion center, and the Np(2) atom occupies a general position. The structure of 1 was additionally refined, and the structures of 1 and 2 were compared. Both compounds have a similar structure, but the structure of 2 is less ordered, and the formation of both structures is influenced by hydrogen bonds involving water molecules and [NpO4(OH)2]3– ions. In the structure of 1, hydrogen bonds of type O–H···O form a three-dimensional network. In the structure of 2, the O–H···O hydrogen bonds are weaker and form a two-dimensional network. In the structure of 1, there are two water molecules per [NpO4(OH)2]3– anion, and in the structure of 2, 4/3 water molecules. Needle-like phase 2 in contact with solutions transforms into stable platelike phase 1 with dense packing and a three-dimensional system of hydrogen bonds. The size of needle-like crystals increases, and the rate of their transformation into platelike crystals decreases with increasing alkali concentration and decreasing temperature. The influence of the experiment conditions on the interaction of Np(VII) with [Co(NH3)6]3+ ions in weakly alkaline (0.05–0.15 M) solutions was also studied. The precipitates formed are characterized by the ratio [NpO4(OH)2]3–: [Co(NH3)6]3+ = 2: 1 and are identified as the known compound LiCo(NH3)6Np2O8(OH)2·2H2O.

Radiochemistry. 2017;59(2):124-133
pages 124-133 views

Modeling of systems with aqueous solutions of UO22+ salts. Asymmetric model of excess thermodynamic functions, based on virial expansion of the Gibbs free energy of the solution, VD-AS

Charykov N.A., Semenov K.N., Kurilenko A.V., Keskinov V.A., Letenko D.G., Kulenova N.A., Zolotarev A.A., Klepikov V.V.

Abstract

An asymmetric model of virial expansion of the Gibbs free energy of solution, VD-AS, was suggested. Partial and molar thermodynamic functions of UO2(ClO4)2–H2O, UO2Cl2–H2O, and UO2(NO3)2–H2O binary solutions at 25°C were calculated using this model. The calculations show that the solutions are characterized by different, sometimes extremely large, deviations from ideality. The suggested model is considerably more accurate and stable than the most widely used Pitzer’s model of electrolyte solutions.

Radiochemistry. 2017;59(2):134-142
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Mathematical modeling of extraction of nitric acid, actinides, and fission products into 30% TBP in halogenated diluents using A.M. Rozen’s model

Puzikov E.A., Kudinov A.S., Blazheva I.V., Sytnik L.V., Shishkin D.N., Goletskii N.D., Zilberman B.Y.

Abstract

The effect of a series of halogenated diluents [bis(octafluoroamyloxy)methane, phenyl trifluoromethyl sulfone, methyl dodecafluoroheptyl ether, m-nitrobenzotrifluoride, hexachlorobutadiene, CHCl3, CCl4] on the extraction of spent nuclear fuel solution components [HNO3, U(VI), An(IV), Zr, and Tc] into 30% TBP was studied and mathematically described using improved A.M. Rozen’s model. Comparison with the TBP–paraffins extraction system was made.

Radiochemistry. 2017;59(2):143-151
pages 143-151 views

Sorption of uranium from waste effluent solutions by mesoporous carbon impregnated with trioctylamine

Morsy A.M., Ali A.H.

Abstract

A new mesoporous adsorbent for uranium removal from waste effluents was prepared, characterized, and impregnated with trioctylamine. The adsorption efficiency was investigated as a function of pH, contact time, initial uranium concentration, competing ions, solid/liquid ratio, and temperature using batch sorption techniques. The maximum adsorption capacity was 21.9 mg g–1 at pH 5. The equilibrium data fit well with the Langmuir adsorption isotherm. Kinetic study showed that the process was fast and reached equilibrium within 60 min. The kinetic data fit well with the pseudo-second-order law. Thermodynamic data show that the process is spontaneous and exothermic.

Radiochemistry. 2017;59(2):152-159
pages 152-159 views

Sorption of 137Cs from seawater onto resorcinol–formaldehyde resin

Egorin A.M., Palamarchuk M.S., Tokar’ E.A., Tutov M.V., Azarova Y.A., Tananaev I.G., Avramenko V.A.

Abstract

Sorption of 137Cs from seawater onto a selective cation exchanger based on resorcinol–formaldehyde resin was studied. The maximal distribution coefficient of 137Cs at the ratio S: L = 1: 1000 is (4.1–4.5) × 103 cm3 g–1. The sorption-selective characteristics of the resin are negatively affected by alkaline earth meal ions. In the dynamic regime, the operation life of the resorcinol–formaldehyde resin exceeds 700 bed volumes with more than 95% efficiency of cesium sorption. More than 95% of 137Cs is eluted with a 1–3 M HNO3 solution. The eluate volume does not exceed 10 bed volumes.

Radiochemistry. 2017;59(2):160-165
pages 160-165 views

Removal of 90Sr from nitric acid solutions with sorbents based on di-tert-butyldicyclohexyl-18-crown-6

Milyutina V.V., Nekrasova N.A., Dovhyi I.I., Bezhin N.A., Baulin V.E., Tsivadze A.Y.

Abstract

A series of impregnated sorbents based on di-tert-butyldicyclohexyl-18-crown-6 (DTBDCH18C6), various diluents (1-octanol, nitrobenzene, telomeric alcohol n3), and supports (Porolas-Т, LPS-500, hydrophobized silica gel) for removing tracer and weighable amounts of Sr ions from nitric acid solutions were prepared. The distribution coefficient of tracer amounts of 90Sr on all the synthesized sorbents increases with an increase in the HNO3 concentration in the range 1–7 M. The most pronounced increase in the sorption occurs with an increase in the HNO3 concentration to 3 M. The maximal distribution coefficient of 90Sr (Kd = 158 cm3 g–1) is reached for the sorbent based on DTBDCH18C6 and 1-octanol in 7 M HNO3. Experiments on sorption of weighable amounts of Sr2+ ions show that the static capacity of all the prepared sorbents for Sr in nitric acid solutions amounts to 4.3, 9.2, and 8.4 mg g–1 for the sorbents based on 1-octanol, nitrobenzene, and telomeric alcohol n3, respectively. The synthesized sorbents are suitable for radioanalytical determination of Sr radionuclides in liquid radioactive waste and in radioactively contaminated natural objects.

Radiochemistry. 2017;59(2):166-169
pages 166-169 views

Development of a new radioanalytical technique for the determination of manganese(II) using potassium periodate

Mandal M., Basu S.

Abstract

A radiometric method based on redox substoichiometry was applied to accurate and precise determination of manganese. The proposed technique is based on the substoichiometric oxidation of bivalent manganese to permanganate ions with potassium periodate, followed by isolation of the oxidized species by the extraction with tri-n-octylamine in chloroform. The method was successfully applied to the estimation of manganese content of various certified ores and alloys.

Radiochemistry. 2017;59(2):170-174
pages 170-174 views

Proving the completeness of plutonium dioxide dissolution and evaluating the trueness of the procedure for determining the gravimetric plutonium content by automatic coulometric titration

Momotov V.N., Erin E.A., Zakharova L.V.

Abstract

The influence of various factors on the completeness of transfer of crystalline PuO2 into solution by fusion with NaHSO4, followed by dissolution of the fusion cake in 1 M HClO4, was studied. The process parameters such as temperature, PuO2 to NaHSO4 weight ratio, and fusion time were optimized. The completeness of the PuO2 dissolution under the chosen conditions was proved, and the trueness of the procedure for coulometric titration of Pu(VI) with electrochemically generated Fe(II) ions was evaluated.

Radiochemistry. 2017;59(2):175-180
pages 175-180 views

Radioimmunochemical studies for development of a solid-phase radioimmunoassay system using coated beads for the assessment of human chorionic gonadotropin

Sallam K.M., El-Bayoumy A.S., Mehany N.L.

Abstract

A method was developed for immobilization of prepared human chorionic gonadotropin (β-hCG) antisera on fresh plastic beads through a covalent immune bridge. Such covalent immune-coated antisera on plastic beads were used in the development of a noncentrifugation radioimmunoassay. 125I-β-hCG was prepared using different oxidizing agents. The solid-phase RIA system developed was found to well compete with the conventional method.

Radiochemistry. 2017;59(2):181-187
pages 181-187 views

Polymer formulations for “dry” decontamination of the equipment and premises of nuclear power plants

Voronik N.I., Toropova V.V.

Abstract

Polymer composite formulations for decontamination were developed on the basis of a polyvinyl alcohol solution as a binder with active additives (HNO3, HBF4, 1-hydroxyethane-1,1-diphosphonic acid and its triammonium salt, and a synthetic detergent) and fillers (natural rottenstone; rottenstone modified with nickel and copper ferrocyanides; dolomite modified with nickel ferrocyanide; clinoptilolite modified with iron(III) and calcium chlorides, sodium phosphate, and potassium ferrocyanide; hydrolytic lignin). The developed polymer composite materials (pastes) exhibit high decontaminating ability (DF = 102–103) and low adhesion to the tested surfaces of stainless and carbon steels (including painted surfaces), plastic compound, self-leveling floors, and Teflon surface.

Radiochemistry. 2017;59(2):188-192
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Microbiological treatment of oil-containing radioactive waste prior to cementation

Tregubova V.E., Safonov A.V., Babich T.L., Proshin I.M., Zakharova E.V., German K.E.

Abstract

Microbiological oxidation of liquid organic radioactive waste (ORW), spent vacuum and transformer oils, is described. The physicochemical properties of oils and their structural-group composition before and after using in the process cycle were studied. Changes in the structural-group composition and physicochemical parameters of oils upon microbiological treatment were determined. The distribution of radionuclides between the organic and aqueous phases upon microbiological treatment was studied by the example of model ORW containing 137Cs, 90Sr, 238Pu, and 241Am. The compatibility of oils subjected to microbiological treatment with the cement compound intended for ORW disposal was evaluated. The biological step of the radioactive oil processing leads to a decrease in the weight and volume of the organic radioactive waste and increases its amount that can be incorporated into the cement compound (to 30 vol %) without deterioration of the strength characteristics of the cement.

Radiochemistry. 2017;59(2):193-202
pages 193-202 views

Sorption of long-lived radionuclides onto main types of rocks of the Novaya Zemlya Archipelago

Dubasov Y.V., Pilyutik A.A., Shagin B.O.

Abstract

The ability of black carbonaceous siltstones and silt sandstones, lime sandstones, gray limestones, carbon–silicon carbonate schists with pyrite, and other rocks that most widely occur on the Novaya Zemlya Archipelago to sorb 137Cs, 90Sr, 239+240Pu, and 241Am was studied. The distribution coefficients Kd (cm3 g–1) are as follows: for 239+240Pu, 2.7 × 103–7.7 × 103; for 241Am, 2.5 × 103–1.8 × 104; and for 137Cs, 1.1 × 102–2.0 × 103. Strontium-85(90) it not noticeably sorbed (within the measurement uncertainty) by any of the rocks studied. 239+240Pu, 241Am, and 137Cs are strongly sorbed onto the rocks studied and are not noticeably desorbed from them with distilled water. The data obtained are required for predicting the migration of long-lived radionuclides generated by nuclear explosion with surface waters from test sites on the Novaya Zemlya Archipelago.

Radiochemistry. 2017;59(2):203-207
pages 203-207 views

Lung cancer risks due to the radon in cigarette tobacco

Ridha A.A., Hasan H.A.

Abstract

Thirty-one tobacco samples were evaluated for the activity concentrations of radon and radium using solid-state nuclear track detectors (CR-39). The detectors were exposed for a period of 150 days to different types of cigarette tobacco. The highest values of 364 Bq m–3 for radon and 31.4 Bq kg–1 for radium were obtained for MIA2 sample, and the lowest values of 20.2 Bq m–3 for radon and 1.74 Bq kg–1 for radium, for SUM sample. According to the estimate, this range of radon levels corresponds to the lung cancer incidence in the range 22–396 cases per million smoker per year. The annual effective dose in general and for lungs in particular, the surface and mass exhalation rate, the equivalent equilibrium concentration of radon, and absorbed dose to tissues and lungs were calculated. The highest values were obtained for MIA2 sample, and the lowest values, for SUM sample.

Radiochemistry. 2017;59(2):208-214
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Distribution of 210Ро in lichen thalli

Puchkova E.V., Eremin V.V., Bogdanova O.G., Gimel’brant D.E., Stepanchikova I.S.

Abstract

Distribution of 210Po in thalli of soil and wood (epiphytic) lichens was studied. Four fractions containing the corresponding 210Ро forms were obtained by sequential extraction: (1) intercellular, (2) extracellular, (3) intracellular, and (4) insoluble thallus residue. The 210Ро uptake by lichens is mainly passive, as the total content of the radionuclide in fractions 1, 2, and 4 reaches 88–97%. From 3 to 12% of 210Ро is taken up actively (fraction 3), and for soil lichens this parameter is approximately 2.75 times higher than for epiphytic lichens. Presumably, 210Ро is supplied into soil and epiphytic lichens in the form of different chemical compounds and is therefore characterized by different bioavailability.

Radiochemistry. 2017;59(2):215-218
pages 215-218 views