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Vol 58, No 5 (2016)

Article

Cation–cation interaction in mixed-element Th(IV)/Np(V) chlorides, [Th(NpO2)6(H2O)8(OH)Cl9]·H2O and [Th(NpO2)6(H2O)9Cl9]Cl

Charushnikova I.A., Fedoseev A.M., Krot N.N.

Abstract

The compounds [Th(NpO2)6(H2O)8(OH)Cl9]·H2O (I) and [Th(NpO2)6(H2O)9Cl9]Cl (II), in which mixed-element Th(IV)/Np(V) cation–cation interaction is observed, were isolated in the form of single crystals and studied by X-ray diffraction. The NpO2+···NpO2+ cation–cation bonds link the dioxocations into six-unit rings, and the NpO2+···Th4+ bonds link these rings into a three-dimensional network. The compounds also contain a hydroxide ion incorporated in the Th4+ coordination surrounding or a chloride ion located in the interlayer space, depending on the synthesis conditions. The Np(V) pentagonal bipyramids in I and II are characterized by equal, within the uncertainty, bond lengths. The equatorial planes of the bipyramids are formed by three Cl anions, oxygen atom of the adjacent NpO2+ cation, and oxygen atom of the water molecule. The Th4+ cations in I and II have the coordination surrounding in the form of tricapped trigonal prisms (CN 9) whose quadrangular lateral faces are formed by the oxygen atoms of the NpO2+ cations and are capped by three water molecules. The Th4+ cations in I and II are arranged in the interlayer space, binding three cyclic moieties from each of the two adjacent layers.

Radiochemistry. 2016;58(5):445-450
pages 445-450 views

Synthesis and structure of the complex of uranyl citraconate with urea

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

Abstract

Crystals of [UO2(C5H4O4)(urea)2], where C5H4O42– is citraconate ion, were prepared and studied by IR spectroscopy and single crystal X-ray diffraction. The structure of the crystals is formed by chains having the same composition as the compound as a whole and belonging to the crystal-chemical group AТ11M21 (A = UO22+, Т11 = C5H4O42–, M1 = urea) of uranyl complexes. Comparative analysis of nonvalent interactions in the structures of uranyl complexes with citraconate ions was performed by the method of molecular Voronoi–Dirichlet polyhedra.

Radiochemistry. 2016;58(5):451-456
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Synthesis and structure of dodecamolybdates of tetravalent cerium, thorium, uranium, neptunium, and plutonium

Charushnikova I.A., Gogolev A.V., Grigor’ev M.S., Fedoseev A.M.

Abstract

A series of isostructural compounds of the composition Na7H[EMo12O42]·12H2O, where E(IV) = Ce, Th, U, Np, or Pu, were synthesized and structurally characterized. In the [EMo12O42]8– heteropolyanion (HPA), the central E(IV) atom is surrounded by six Mo2O9 groups, each constituted by two octahedra sharing a common face. The coordination polyhedron (CP) of the central atom is a weakly distorted icosahedron with the mean E(IV)–О bond lengths of 2.498, 2.529, 2.500, 2.490, and 2.488 Å for Ce, Th, U, Np, and Pu, respectively. In the structure of the compounds Na7H[EMo12O42]·12H2O, there are two crystallographically independent sodium atoms: Na(1) and Na(2). The oxygen surrounding of the Na(1) atom is formed by the terminal oxygen atoms of two heteropolyanions adjacent along [001], and its coordination polyhedron is an octahedron. The surrounding of the Na(2) atom (a six-vertex polyhedron) is formed by three terminal oxygen atoms of three Mo2O9 groups belonging to the same HPA and by three water molecules. The coordination polyhedra of the Na(2) atoms are linked with each other via common oxygen atoms of Ow(2) water molecules to form a chain “winding” around the 31 screw axis. The heteropolyanions and Na+ cations in the crystal form a framework constructed in a fashion characteristic of Dexter–Silverton type anions, with the coordination via three terminal oxygen atoms of three Mo2O9 groups. Excess negative charge of HPA is compensated by the proton localized on one of the six bridging O atoms. In the Mo2O9 doubled octahedra, the Mo–O bonds with the О atoms bonded to E(IV) and forming the edge of the common face are sensitive to the kind of the central atom.

Radiochemistry. 2016;58(5):457-465
pages 457-465 views

Electrochemical properties and dissolution of UPd3 in nitric acid solutions

Zavarzin S.V., Maslennikov A.G., Gedgovd K.N., Bulatov G.S., Vlasova I.E.

Abstract

Electrochemical properties of the intermetallic compound UPd3 in 0.5–8 M HNO3 solutions were studied by linear voltammetry. In 0.5–2 M HNO3 solutions, the UPd3 surface is in the passive state. At HNO3 concentrations exceeding 4 M, the alloy passivation was not observed. The previously unknown electrochemical characteristics of UPd3 in nitric acid solutions were obtained using the Tafel equation. The values of Е(i = 0) and vcorr increased from 39 mV and 38 μg cm–2 h–1 in 0.5 M HNO3 to 821 mV and 11 mg cm–2 h–1 in 8 M HNO3, respectively. Dissolution experiments have shown that UPd3 can dissolve in HNO3 solutions of concentration exceeding 4 M at room temperature. In 8 M HNO3, the dissolution rate can reach 17 mg cm–2 h–1 at 25°С, with the dissolution being virtually equimolar and accelerating with time.

Radiochemistry. 2016;58(5):466-472
pages 466-472 views

Mathematical model of precipitation of barium and strontium nitrates from nitric acid solutions and their mutual effect

Puzikov E.A., Mishina N.E., Zilberman B.Y.

Abstract

A mathematical model describing the solubility of barium, strontium, and lead nitrates in nitric acid solutions containing 0 to 14 M HNO3 in the temperature range from 0 to 90°С with the error no larger than 7% was developed. The model is based on the reactions of metal precipitation in the form of Me(NO3)2 at HNO3 concentrations of up to 7–8 M and Ме(NO3)2·2HNO3 at higher nitric acid concentrations, and also on the assumed formation of soluble metal nitrate complexes MeNO3+. A sharp increase in the barium solubility at HNO3 concentrations lower than 0.5 M and temperatures of 50 and 90°С was interpreted assuming the possible formation of dimeric oxocations Ba2O2+ or associates Ba2(OH)22+. A model describing the solubility of barium nitrate in the presence of strontium nitrate in HNO3 solutions at HNO3 concentrations in the range from 0 to 5 M was also suggested.

Radiochemistry. 2016;58(5):473-479
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Effect of 239Pu α-radiation on its extraction from nitric acid solutions with a 30% solution of tri-n-butyl phosphate in Isopar-M

Dzhivanova Z.V., Tkhorzhnitskii G.P., Belova E.V., Myasoedov B.F.

Abstract

Extraction of 239Pu from 4 M НNО3 with an HNO3-saturated 30% solution of tri-n-butyl phosphate (TBP) in Isopar-M in the cyclic mode was studied. As a result of four-month contact with an aqueous НNО3 solution containing 0.11 M Pu(IV), the organic phase absorbed the total α-radiation dose of 380 kGy. The fraction of the residual Pu in the organic phase after stripping increases by a factor of 5–7 as the absorbed dose is increased from 32 to 263 kGy. The residual concentration of Pu in the organic phase after 45–50 stripping cycles (which corresponds to the irradiation dose with accelerated electrons of 120–150 kGy) increases by a factor of 3–4. The Pu distribution ratio in the extraction step in the cyclic mode varies only slightly.

Radiochemistry. 2016;58(5):480-485
pages 480-485 views

Thermal stability and radiation resistance of trifluoromethyl phenyl sulfone in the presence of nitric acid

Belova E.V., Nazin E.R., Skvortsov I.V., Sokolov I.P., Rodin A.V., Stefanovsky S.V., Myasoedov B.F.

Abstract

The effect of HNO3 on the thermal stability and radiation resistance of trifluoromethyl phenyl sulfone (FS-13) used as extractant diluent in high-level waste partitioning was studied. Heating of FS-13 in the presence of 14 M HNO3 is not accompanied by exothermic effects up to 160°С. The amount of gaseous products released in the course of heating the system consisting of FS-13 and HNO3 and the composition of the major radiolysis products of the system components at irradiation doses of up to 0.5 MGy were determined.

Radiochemistry. 2016;58(5):486-490
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Removal of cesium and strontium radionuclides from aqueous media by sorption onto magnetic potassium zinc hexacyanoferrate(II)

Pshinko G.N., Puzyrnaya L.N., Shunkov V.S., Kosorukov A.A., Demchenko V.Y.

Abstract

Removal of Cs and Sr radionuclides from aqueous media by sorption onto magnetic potassium zinc hexacyanoferrate(II) was studied. This magnetic sorbent is more efficient and selective in sorption of Cs radionuclides, compared to Sr radionuclides, in a wide pH range, 2.8–9.0. The performance of magnetic potassium hexacyanoferrate(II) in removal of Cs and Sr radionuclides is mainly determined by the kind and concentration of macrocomponents (Na+, K+, Ca2+) of natural waters and liquid radioactive waste.

Radiochemistry. 2016;58(5):491-497
pages 491-497 views

A modified electrochemical procedure for isolating 177Lu radionuclide

Boldyrev P.P., Kurochkin A.V., Proshin M.A., Chuvilin D.Y., Yashin Y.A.

Abstract

A cell for isolating 177Lu from a neutron-irradiated 176Yb target was developed. The procedure involves a combination of two processes: contact reduction of Yb from acetate–chloride solution on sodium amalgam, followed by electrolysis of the solution on a mercury cathode. The process conditions were chosen so that the adjustment of the working solution characteristics (composition, pH, etc.) in going from contact reduction to electrolysis was not required. Both processes are performed in one cell, which reduces the 177Lu loss. On an installation consisting of two cells, the decontamination factor of the 177Lu solution from Yb of up to 106 was reached, which is necessary for obtaining a 177Lu preparation of high specific activity.

Radiochemistry. 2016;58(5):498-505
pages 498-505 views

Preparation and properties of 68Ga complexes with RGD peptide derivatives

Bubenshchikov V.B., Maruk A.Y., Bruskin A.B., Kodina G.E.

Abstract

Conditions allowing preparation of 68Ga complexes with RGD peptide derivatives with no less than 95% radiochemical purity were determined. The complexes are stable in blood plasma for the time sufficient for performing a diagnostic investigation.

Radiochemistry. 2016;58(5):506-512
pages 506-512 views

Extraction centrifugal generator of 188Re and radiopharmaceuticals based on it for radionuclide therapy

Tsivadze A.Y., Filyanin A.T., Romanovskii V.N., Zykov M.P., Kodina G.E., Malysheva A.O., Filyanin O.A., Nepomnyashchii O.N.

Abstract

The results of the development of a medical-purpose extraction 188Re generator and of 188Re radiopharmaceuticals are presented. The main advantage of this generator is the possibility of using as starting material tungsten oxide of natural isotope composition, irradiated in a reactor with medium neutron flux [(1.0–1.4) × 1014n cm–2 s–1]. Separation of the parent 188W and daughter 188Re was performed in a centrifugal semicounter-current contactor developed at the Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences. The 188Re yield is about 90%, and the radiochemical purity (Na188ReO4 content) is ≥95%. The content of the 188W impurity is less than 1 × 10–3% relative to the 188Re activity, and the content of other radionuclides is less than 1 × 10–4%. The resulting Na188ReO4 solution was registered as “Active pharmaceutical substance” and was used in the development and subsequent preclinical trials of several radiopharmaceuticals for radionuclide therapy of pain syndrome accompanying the development of cancer metastases into the skeleton, and also for radiosynovectomy.

Radiochemistry. 2016;58(5):513-520
pages 513-520 views

Preclinical evaluation of 99mTc-histidine as a possible tumor imaging agent

Ibrahim I.T., Abdelhalim S.M., Farouk N.

Abstract

Radiolabeling of histidine (Hist), an essential amino acid, with 99mTc was performed. The radiochemical yield higher than 95% was achieved with stannous chloride as a reducing agent. Factors affecting the radiochemical yield (histidine amount, stannous chloride amount, reaction time, pH of the reaction mixture) were studied in detail, and the reaction conditions were optimized. In vitro stability of the radiolabeled complex was checked, and it was found to be stable for up to 6 h. 99mTc-Hist was injected intravenously into normal and tumor-bearing mice. Biodistribution studies revealed that the 99mTc-Hist uptake in tumor sites was 10 and 16% ID/g in ascites and 7 and 9.2% ID/g in thigh solid tumor at 60 and 120 min post injection, respectively. The amount of 99mTc-Hist in ascites and solid tumor increased with time and then decreased slowly. Thus, 99mTc-Hist can be used as a potential agent for imaging tumor sites.

Radiochemistry. 2016;58(5):521-527
pages 521-527 views

Preparation of a carbon-14 analog of 2-[2-(4-(dibenzo[b, f][1,4]thiazepin-11-yl)piperazin-1-yl)ethoxy]ethanol

Saadatjoo N., Javaheri M., Saemian N., Amini M.

Abstract

2-[2-(4-(Dibenzo[b, f][1,4]thiazepin-11-yl)piperazin-1-yl)ethoxy]ethanol (Quetiapine) labeled with 14C in 11-position was synthesized in five steps from [carboxy-14C]anthranilic acid. The key precursor of the target product is [11-14C]dibenzothiazepin-11(10H)-one. The reaction is performed as one-pot process.

Radiochemistry. 2016;58(5):528-531
pages 528-531 views

Diffusion of some critical radionuclides in mineral-like ceramic materials

Tsvetkov V.I., Ivanov I.A., Nechaev A.F.

Abstract

The diffusion coefficients and activation energy of diffusion of 22Na, 90Sr, 152Eu, and 241Am radionuclides in zirconolite ceramics prepared by cold crucible induction melting (CCIM), of 22Na, 90Sr, 137Cs, 152Eu, and 241Am in Synroc-C ceramics prepared by hot pressing (HP) and CCIM, and of 22Na and 152Eu in the ceramic from the Lawrence Livermore National Laboratory (the United States), synthesized by cold pressing (CP) and sintering, and also the diffusion mobility of 90Sr, 137Cs, and 241Am in the chromium-containing sphene glass ceramic prepared by CCIM were determined by the method of integral residual activity. In the temperature interval 573–923 K, the 22Na radionuclide is the most mobile and 241Am is the least mobile. The differences between the diffusion coefficients reach 4–5 orders of magnitude. The diffusion coefficients of the examined radionuclides in the ceramic depend both on the preparation procedure (HP, CP, or CCIM) and on the initial charge components when the same procedure is used for preparing the ceramic. Negative values of the activation entropy of the diffusion of 22Na, 90Sr, 152Eu, and 241Am in ceramics suggest that the mass transfer of radionuclides in them occurs not by the vacancy mechanism but by the interstitial mechanism and, probably, in part along the facilitated migration pathways (grain boundaries, pore surfaces, micro- and macrocracks).

Radiochemistry. 2016;58(5):532-537
pages 532-537 views

An ultradisperse technology for consolidation of fission product concentrates in a ceramic container crucible

Kuznetsov R.A.

Abstract

An ultradisperse technology is suggested for consolidation of partitioned product concentrates in an iron–lanthanum silicophosphate ceramic host material. The technology is economically advantageous because of the use of readily available reagents and raw materials and takes a short time owing to the composite structure of the host material. The latter factor also ensures high corrosion resistance of the host material. The process allows the development of a robotic system for nuclear waste packing directly in the container crucible. It is appropriate to isolate the ready nuclear containers in a superdeep borehole repository.

Radiochemistry. 2016;58(5):538-544
pages 538-544 views

A carbon composite based on pyrolyzed diphthalocyanines for immobilization of high-level waste from nuclear industry

Tikhonov V.I., Kapustin V.K., Lebedev V.T., Sovestnov A.E., Bairamukov V.Y., Mishin K.Y.

Abstract

A new procedure for immobilization of high-level waste from spent nuclear fuel (SNF) of nuclear power plants (NPP) is suggested. The HLW immobilization process consists in the radionuclide transfer into the form of acetates, followed by synthesis of their diphthalocyanines and their subsequent pyrolysis in an inert medium. Real raffinate solutions from reprocessing of SNF of Novovoronezh NPP were used as HLW. The efficiency of the immobilization of radionuclides (mainly REE and minor actinides) was found to be higher than 99%. The thermal stability, chemical durability (leaching with aqueous solutions with pH from 2 to 9), and radiation resistance of the samples were evaluated using α-, β-, and γ-ray spectrometry. The evolution of the structure of the pyrolyzed diphthalocyanines in the temperature range 800–1600°C was studied by small-angle neutron scattering, X-ray diffraction analysis, and atomic force microscopy. The results obtained have confirmed the hypothesis that the pyrolysis of diphthalocyanines yields a branched network of carbon atom nanoclustes of size from 5 to ~150 nm, ensuring efficient retention of radionuclides in the host material. The host material is comparable in the thermal stability, i.e., in the degree of radionuclide retention at 1000–1200°С, with borosilicate or phosphate glasses, which are the most widely used host materials for radioactive waste immobilization, and considerably surpasses them in the resistance to leaching and radiation.

Radiochemistry. 2016;58(5):545-555
pages 545-555 views

Distribution of 210Pb in the surface sediments of major rivers of coastal Kerala, South India

Venunathan N., Narayana Y.

Abstract

The distribution of 210Pb in the sediment samples of major rivers of coastal Kerala, namely, Bharathapuzha, Periyar, and Kallada, was studied systematically. The activity of 210Pb was estimated through 210Po by radiochemical separation and subsequent deposition on a silver disc. The α-activity was then counted using a ZnS(Ag) counter of 30% efficiency, and the activity was calculated. The mean activities of 210Pb in the sediment samples of Bharathapuzha, Periyar, and Kallada rivers were found to be 13.5 ± 1.2, 89 ± 3, and 61 ± 2 Bq kg–1, respectively. Good correlation was found between the 210Pb activity and organic matter percentage and clay content for Periyar and Kallada rivers.

Radiochemistry. 2016;58(5):556-559
pages 556-559 views

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