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Vol 59, No 1 (2017)

Article

Coulometric methods for uranium and plutonium determination

Momotov V.N., Erin E.A.

Abstract

Data on coulometric methods for U and Pu determination in various nuclear materials are presented, analyzed, and summarized. Coulometric determination methods at controlled current and controlled potential are considered. The main principles of the U and Pu determination procedures based on the use of the UO22+/U4+, Pu4+/Pu3+, and PuO22+/Pu4+ redox couples are presented. Various methodical factors influencing the error of the U and Pu determination, such as sample weight; supporting electrolyte composition; oxidation and reduction potentials; current; electrode material, shape, and activation procedure; impurity elements, etc., are discussed. Procedures for joint coulometric determination of U and Pu are considered separately. The main methods used by the authors for eliminating the mutual effect of U and Pu in their joint determination are described.

Radiochemistry. 2017;59(1):1-25
pages 1-25 views

Crystal-chemical features of baric polymorphism of actinides

Serezhkin V.N., Savchenkov A.V., Serezhkina L.B.

Abstract

Crystal-chemical analysis of actinide baric polymorphs was performed on the basis of Voronoi–Dirichlet (VD) tessellation. The second moment of inertia of the VD polyhedron (G3) and the displacement of the atom nucleus from the center of gravity of its VD polyhedron (DA) were suggested as descriptors acting as criteria for revealing 5f interactions between the actinide atoms. Pressure elevation is accompanied, as a rule, by an increase in G3 for Th, Pa, Am, Cm, Bk, and Cf, whereas for U and Pu it leads to a decrease in G3. Topologically equivalent flat (Th-hP) or corrugated (Pa-hP, α-U, Вk-III) 44 networks are formed in these high-pressure phases owing to the shortest (covalent) bonds between the actinide atoms, whereas a diamond-like framework is formed in the structures of An-III or An-IV (An = Am, Cm, Cf) and Cm-V, and Pu4 molecules are formed in hexagonal Pu-hP.

Radiochemistry. 2017;59(1):26-34
pages 26-34 views

Complex of uranyl citraconate with dimethylacetamide: Synthesis and structure

Serezhkina L.B., Grigor’ev M.S., Novikov S.A., Kolotilina M.A., Serezhkin V.N.

Abstract

The complex [UO2(C5H4O4)(Dmа)] (I), where C5H4O42– is citraconate ion and Dmа is dimethylacetamide, was synthesized and studied by single crystal X-ray diffraction analysis. The complex has layered structure and belongs to crystal-chemical group AQ21M1 (A = UO22+, Q21 = C5H4O42–, M1 = Dmа) of uranyl complexes. Structural features of all the known uranyl complexes with citraconate anions are considered. Nonvalent interactions in the crystal structure of I are characterized using the method of molecular Voronoi–Dirichlet polyhedra. The IR spectrum of I is analyzed.

Radiochemistry. 2017;59(1):35-40
pages 35-40 views

Electrochemical studies of technetium–ruthenium alloys in HNO3: Implications for the behavior of technetium waste forms

Poineau F., Koury D.J., Bertoia J., Kolman D.G., Mausolf E.J., Goff G.S., Kim E., Jarvinen G., German K.E., Czerwinski K.R.

Abstract

The electrochemical behavior of Tc–Ru alloys (Ru content, at. %: 3.2, 5.2, 20.1, 24.7) in 1 M HNO3 was studied. The transpassivation potentials (Etp) of Tc–Ru alloys were determined by linear voltammetry. The results show that the transpassivation potentials of the alloys increase with the Ru content. To understand the dissolution mechanism, electrolysis experiments at 1.2 V vs. Ag/AgCl were performed; the corrosion products of the alloys were characterized in solution by UV-visible spectroscopy and electrospray ionization mass spectrometry (ESI-MS). For Ru, a polymeric Ru(IV) species was detected, while for Tc the speciation was dominated by TcO4.

Radiochemistry. 2017;59(1):41-47
pages 41-47 views

Electrochemical dissolution of Тс–Ru alloys in nitric acid solutions

Rotmanov K.V., Maslennikov A.G., Zakharova L.V., Goncharenko Y.D., Peretrukhin V.F.

Abstract

Electrochemical dissolution of Тс–19 wt % Ru, Тс–45 wt % Ru, and Тс–70 wt % Ru in 1 to 6 M HNO3 solutions in the amperostatic mode was studied. In the solutions formed from anodic dissolution of Тс–Ru alloys, Ru is present in the form of Ru(IV), and Тс, in the form of Тс(VII). A kinetic study of the electrochemical dissolution of the Тс–70 wt % Ru alloy in the examined interval of HNO3 concentrations showed that the alloy dissolved congruently and the Тс(VII) and Ru(IV) accumulation in the solution linearly depended on time. Anodic dissolution of Tc–Ru alloys with lower Ru content was also characterized by a linear increase in the Тс(VII) concentration in the solution with time. On the other hand, formation of poorly soluble hydrated Ru(IV) oxide on the electrode surface was observed simultaneously with accumulation of soluble Ru(IV) species in solution. The rate of electrochemical dissolution of the Тс–70 wt % Ru alloy linearly increased with increasing HNO3 concentration. The rates of electrochemical dissolution of Tc, determined for alloys with lower Ru content, were independent of the HNO3 concentration in the electrolyte. Oxidation of water with the evolution of oxygen on the surface of Tc–Ru alloys was observed simultaneously with the anodic dissolution of Tc and Ru. This process leads to a decrease in the current efficiency of the Tc and Ru dissolution. Examination of the corrosion damage of the working electrode surfaces by scanning electron microscopy shows that the electrochemical dissolution of Tc–Ru alloys leads to uniform corrosion of their surface.

Radiochemistry. 2017;59(1):48-53
pages 48-53 views

Effect of carbon impurity in irradiated mixed uranium–plutonium nitride on the phase composition upon β-decay of fission products

Bulatov G.S., Gedgovd K.N., Maslennikov A.G., Lyubimov D.Y.

Abstract

As shown by thermodynamic modeling, accumulation of fission products in the course of irradiation of mixed uranium–plutonium nitride containing 0.25 wt % C impurity leads to the formation of a multicomponent carbonitride solid solution containing U, Pu, Am, Np, Zr, Y, lanthanides, and also separate carbide (UMoC2, U2RuC2, URu3C0,7, BaC2, SrC2) and nitride (U2N3) phases and intermetallic compounds U(Ru, Rh, Pd)3. The β-decay of metallic radionuclides in separate carbide phases of spent nuclear fuel leads to changes in their chemical compositions. The transformation kinetics of separate dicarbide (89SrC289YC2, 90SrC290YC290ZrC + C, 140BaC2140LaC2140CeC2) and complex carbide (U99MoC2 → UC2 + 99Tc) phases was calculated.

Radiochemistry. 2017;59(1):54-57
pages 54-57 views

Extraction-chromatographic properties and radiation resistance of a solid extractant based on di-2-ethylhexyl hydrogen phosphate

Erin E.A., Momotov V.N., Baranov A.A., Nagaitseva L.V., Konovalova Y.S., Galina Y.A.

Abstract

Extraction-chromatographic properties of LN-B200-S sorbent based on di-2-ethylhexyl hydrogen phosphate were studied. The equilibrium distribution coefficients of Am in the sorbent–HNO3 system, the total exchange capacity, and the capacity to breakthrough were determined. The influence of the absorbed dose on the above parameters was examined. The suggested extraction-chromatographic system was tested with a real solution of spent nuclear fuel from an RBMK-1000 reactor as applied to the recovery of the Am–Cm–Nd fraction.

Radiochemistry. 2017;59(1):58-64
pages 58-64 views

Sorption of cesium and strontium radionuclides onto crystalline alkali metal titanosilicates

Milyutin V.V., Nekrasova N.A., Yanicheva N.Y., Kalashnikova G.O., Ganicheva Y.Y.

Abstract

Sorption of tracer amounts of 137Cs and 90Sr radionuclides from model solutions of various compositions onto synthetic titanosilicates, framework ivanyukite and layered SL3, both synthesized at the Center for Nanomaterials Science, Kola Scientific Center, Russian Academy of Sciences, was studied. Synthetic ivanyukite and titanosilicate SL3 well compete with Termoxid-25 ferrocyanide sorbent in the ability to take up cesium from neutral NaNO3 solutions and from a simulated solution of bottom residue from a nuclear power plant with RBMK reactors. The maximal sorption of 137Cs onto ivanyukite is observed at pH 6–7. The dependence of the 137Cs distribution coefficient (Kd) on ivanyukite on the concentration of sodium and potassium ions in the solution was studied. Potassium ions affect the cesium sorption more strongly than sodium ions do. In the ability to take up 90Sr, synthetic ivanyukite well competes with synthetic zeolite of type A and with the sorbent based on modified manganese dioxide. The dependences of Kd of 90Sr on the concentrations of the Na+ and Ca2+ ions in the solution were determined. Calcium ions affect the strontium sorption more strongly than sodium ions do. Ivanyukite and SL3 show promise as sorbents for removing cesium and strontium radionuclides from multicomponent salt solutions.

Radiochemistry. 2017;59(1):65-69
pages 65-69 views

Sorption behavior of strontium ions in humic acid solutions

Volkov I.V., Polyakov E.V., Denisov E.I., Ioshin A.A.

Abstract

As shown by distribution, thermodynamic modeling, and dispersion analysis methods, the ability of freshly precipitated humic acid to take up Sr(II) ions is influenced by energy heterogeneity of its sorption sites, characteristic of both natural and synthetic samples. It is manifested in that the distribution coefficient Kd exceeds 1.9 × 104 mL g–1 at Sr(II) concentrations in solutions lower than 20 μg L–1 but is equal to 1.9 × 103 mL g–1 at Sr(II) concentrations higher than 1 mg L–1. In solutions with ultralow Sr(II) concentrations, humic acids exhibit high affinity for the humate complex Sr(HA) and do not interact with the complex Sr(HA)2.

Radiochemistry. 2017;59(1):70-78
pages 70-78 views

Removal of volatile radioactive iodine compounds from water vapor–air medium

Kulyukhin S.A., Rumer I.A., Mizina L.V., Yagodkin I.V., Posazhennikov A.M.

Abstract

Sorption of CH3131I and 131I2 from water vapor–air medium onto SiO2–C (2 wt %) composite material and a mixture of SKT-3I with SiO2–Cu0 (10 wt %) was studied. SKT-3I shows high performance in sorption of 131I2 and CH3131I. The degree of localization of 131I2 and CH3131I exceeds 99.99% at ~60°С and gas phase–sorbent contact time τ of ~0.45 s. The degree of sorption of 131I2 and CH3131I onto the SiO2–C (2 wt %) composite material under similar conditions does not exceed ~87 and ~8%, respectively. Experiments on 131I2 and CH3131I sorption onto mechanical mixtures of SiO2–Cu0 and SKT-3I in the weight ratio varied from 1: 4 to 1: 1 showed that the degree of the 131I2 and CH3131I sorption at ~60°С and τ ~0.45 s exceeded 99.95 and 99.0%, respectively. The scheme of layer-by-layer arrangement of SiO2–Cu0 and SKT-3I in the column was examined. It shows promise for use in AUI-1500VM filters in ventilation systems of nuclear power plants.

Radiochemistry. 2017;59(1):79-84
pages 79-84 views

Chemical-spectroscopic determination of impurity elements in concentrated salt products from pyrochemical reprocessing of spent nuclear fuel

Khamdeev M.I., Vasil’eva O.N., Kubasova L.A., Erin E.A.

Abstract

A procedure was developed for separating fission products and impurity elements from concentrated solutions of alkali metal salts by precipitation of carbonates for their subsequent determination by atomic emission spectroscopy. Coprecipitation of Cr, Al, Pb, Fe, Ni, Mo, Cu, Ca, Mg, Eu, Sm, and Gd with various collectors (Zn, Ga, Bi, In, Sc, Sr, Y, Cd) on introducing potassium carbonate into aqueous solutions of potassium sulfate, hydrosulfate, chloride, and nitrate with the salt concentration of 25 to 250 g dm–3 was studied. The optimum composition of the coprecipitants and the precipitation conditions were determined by methods of mathematical experiment design. The procedure developed is applicable to solutions of alkali metal sulfates, chlorides, and nitrates.

Radiochemistry. 2017;59(1):85-91
pages 85-91 views

Preparation and biological evaluation of 99mTc-timonacic acid as a new complex for hepatobiliary imaging

Sanad M.H., El-Tawoosy M., Ibrahim I.T.

Abstract

Timonacic acid (TCA) was successfully labeled with 99mTc. The influence exerted on the reaction by the substrate and reducing agent concentrations, pH of the reaction mixture, and reaction time was examined, and in vitro stability of 99mTc-TCA was evaluated. The maximum labeling yield was 98.5 ± 0.6%. The complex was stable throughout the working period (6 h). A study of in-vivo biodistribution in mice showed that the maximum uptake of 99mTc-TCA in the liver was 22.3 ± 0.3% of the injected activity per gram of the tissue or organ (% ID/g) at 30 min post injection. The clearance from the mice appeared to proceed via the circulation mainly through the kidneys and urine (approximately 56% of the injected dose at 1 h after injection). The liver uptake of 99mTc-TCA is higher than that of 99mTc-UDCA (ursodeoxycholic acid); therefore, 99mTc-TCA shows more promise for liver SPECT.

Radiochemistry. 2017;59(1):92-97
pages 92-97 views

Measuring the radioactivity concentration of 40K and 137Cs and calculating the annual internal doses from ingesting liquid and powdered milk

Alharshan G.A., Aloraini D.A., Al-Ghamdi H., Almuqrin A.H., El-Azony K.M., Alsalamah A.S.

Abstract

Thirty-three samples of powdered milk and thirteen samples of liquid milk (mostly imported from several countries) were collected from the local market in Saudi Arabia to measure the activity concentrations of artificial and natural radionuclides and evaluate the safety of milk for humans. Spectrometric analysis using the HPGe detector was performed. The results show that the activity concentration of 40K in powdered milk ranged between 130 ± 7 and 595 ± 32 Bq kg–1 (average 285 ± 29 Bq kg–1), and that of 137Cs ranged between 0.05 ± 0.02 and 1.3 ± 0.2 Bq kg–1 in powder milk. In liquid milk, the activity concentration of 40K ranged between 40 ± 2 and 98 ± 5 Bq L–1 (average 66 ± 4 Bq L–1), and that of 137Cs was 0.12 ± 0.03 Bq L–1. The annual internal dose for 40K and 137Cs was calculated, and it is lower than the regulated dose.

Radiochemistry. 2017;59(1):98-103
pages 98-103 views

Radon exhalation rate measurement in the environment of Hassan district of southern India

Jagadeesha B.G., Narayana Y.

Abstract

The radon exhalation rate from soil and building materials collected from the Hassan district of southern India was studied by the sealed can technique. The surface exhalation rates of the building materials were found to vary from 13.07 ± 0.19 to 430 ± 9 mBq m–2 h–1 with a mean value of 141 ± 4 mBq m–2 h–1. The surface exhalation rates of the soil samples were found to vary from 36.5 ± 0.8 mBq m–2 h–1 to 376 ± 7 mBq m–2 h–1 with a mean value of 140 ± 4 mBq m–2 h–1. Good positive correlation was observed between the effective radium content and radon exhalation rate for both soil and building materials. Annual effective dose and α-index have also been estimated for the population of the region.

Radiochemistry. 2017;59(1):104-108
pages 104-108 views

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