


Vol 58, No 2 (2016)
- Year: 2016
- Articles: 16
- URL: https://ogarev-online.ru/1066-3622/issue/view/13721
Article
Synthesis and properties of actinide dimolybdate complexes M2[AnO2(MoO4)2]·H2O (M = Rb, Cs; An = Np, Pu)
Abstract
New Np(VI) and Pu(VI) dimolybdates Rb2NpO2(MoO4)2·H2O (I), Cs2NpO2(MoO4)2·H2O (II), Cs2PuO2(MoO4)2·H2O (III), and Rb2PuO2(MoO4)2·H2O (IV) were synthesized under hydrothermal conditions. The crystal structures of the compounds were determined, and their absorption spectra in the UV, visible, and IR ranges were measured. The compounds crystallize in the monoclinic system. Their crystal structure is based on [AnO2(MoO4)2]n2n– anionic layers (An = Np, Pu) formed by (AnO2)O5 pentagonal bipyramids and MoO4 tetrahedra, sharing common vertices. Each An atom in the layer is bonded to other five An atoms via MoO4 tetrahedra with the formation of a 43432 network. The effect of the ionic radius of the outer-sphere cation on the parameters of the crystal structure and features of the absorption spectra is discussed.



Synthesis and structure of crystals of UO2(C2H5COO)2·1.5L (L = methylurea or N,N’-dimethylurea)
Abstract
The compounds UO2(C2H5COO)2·1.5L, where L is methylurea (Meur) or N,N’-dimethylurea (s-Dmur), were synthesized and studied by IR spectroscopy and single crystal X-ray diffraction. Irrespective of the kind of amide L, the structure of the compounds consists of two mononuclear uranium-containing complexes: cationic [UO2(prop)L3]+ and anionic [UO2(prop)3]–, where prop is propionate ion. Both compounds belong to crystal-chemical group AB01M31+ AB01M301 (A = UO22+, B01 = prop–, M1 = L) of uranyl complexes. The composition of 15 stable uranyl complexes that can be formed in the UO22+, B01–prop––L–H2O system was predicted on the basis of the characteristics of the Voronoi–Dirichlet polyhedra from the standpoint of the 18-electron rule.



Synthesis and study of sodium uranate Na2U2O7·6H2O and of products of its dehydration and thermal decomposition
Abstract
Previously unknown sodium uranate of the composition Na2U2O7·6H2O was synthesized by precipitation from solution under hydrothermal conditions at 200°С. The composition and structure of this compound were determined by chemical analysis, X-ray diffraction, IR spectroscopy, and thermal analysis. The dehydration and thermal decomposition of the compound were studied.



Reaction of Np(VI) with cyclohexanediaminetetraacetic acid in HClO4 solutions
Abstract
The stoichiometry of the reaction of Np(VI) with cis-cyclohexanediaminetetraacetic acid (CHDTA, H4chdta) in 0.05 M HClO4 solution was studied by spectrophotometry. With Np(VI) in excess, 1 mol of the complexone converts 4 mol of Np(VI) into Np(V). In 0.115–0.98 M HClO4 solutions (the ionic strength of 1.0 was supported with LiClO4) containing 3–29 mM CHDTA at 20–45°С, Np(VI) at a concentration of 0.2–3.3 mM is consumed in accordance with the first-order rate law until less than 40% of Np(VI) remains. After that, the reaction decelerates. The reaction rate has first order with respect to [CHDTA] and the order of–1.2 with respect to [H+]. The activated complex is formed with the loss of one and two Н+ ions. The activation energy is 82.3 ± 3.8 kJ mol–1.



Gas-phase conversion of U, Sr, Mo, and Zr oxides into water-soluble compounds in an HNO3 (vapor)–air atmosphere
Abstract
Gas-phase conversion of U3O8, MoO3, SrO, ZrO2, and their mechanical mixtures into water-soluble compounds in an HNO3 (vapor)–air atmosphere was studied. In the course of the gas-phase conversion, U3O8 and SrO transform into water-soluble compounds (nitrates, hydroxynitrates), whereas MoO3 and ZrO2 undergo no changes. The principal possibility of separating U from Mo and Zr by gas-phase conversion of the oxides in the HNO3 (vapor)–air atmosphere was demonstrated.



Kinetics of gas-phase conversion of U3O8 into water-soluble compounds in nitrating atmosphere at 25–30°С
Abstract
The kinetics of the gas-phase conversion of U3O8 in NOx–H2O (vapor)–air and HNO3 (vapor)–H2O (vapor)–air atmospheres was fitted by the Kazeev–Kolmogorov–Erofeev equation. The following parameters n and K were obtained: for experiments in NOx–H2O (vapor)–air atmosphere, n = 0.2 ± 0.1 and K = 0.2 ± 0.2 h–1; for experiments in HNO3 (vapor)–H2O (vapor)–air atmosphere, n = 0.3 ± 0.2 and K = 0.03 ± 0.02 h–1 (confidence probability p = 0.95). For the U3O8 conversion in both media, n < 0.5, which suggests the diffusion control of the U3O8 conversion under the action of both HNO3 and NOx.



Effect of salting-out agents on nitric acid distribution between liquid and vapor in the course of evaporation of nitric acid radioactive waste
Abstract
The database on the influence of concentrations of salting-out agents with different cation valence (Li+, Na+, K+, Cs+, NH4+, Mg2+, Ca2+, Cu2+, Zn2+, Al3+, Fe3+, La3+, Pu4+, UO22+ nitrates) and of H2SO4 on the HNO3 distribution between liquid and vapor at atmospheric pressure was verified and expanded by performing equilibrium evaporation experiments in an evaporator without reflux with circulation of the bottoms. This equilibrium can be described by the equation \(\log {\kern 1pt} {\alpha _H} = - 2.35 + 2\log \;{X_{\Sigma N{O_3}}}\) (where \({X_{\Sigma N{O_3}}}\) is the total concentration of nitrate ions in aqueous solution), taking into account partial binding of water due to hydration of the salting-out agent and apparent hydrolysis of polyvalent cations, and also incomplete dissociation of sulfuric acid. The suggested model is valid at \({X_{\Sigma N{O_3}}}\) from 3 to 16 M (azeotrope); at \({X_{\Sigma N{O_3}}}{\text{ < }}\;3\), Raoult’s law is observed (αH = const), which is confirmed by a number of examples. In this model, the additivity of the properties of the salting- out agents, taking into account the concentration of “free” water, is assumed, which allows calculation of the composition of the bottoms and distillate when evaporating waste of any composition from radiochemical plants.



Immobilization of metal cations with titanium phosphate sorbents
Abstract
Dehydration and crystallization of titanium phosphate sorbents saturated with metal cations were studied with the aim of developing methods for immobilization and reliable disposal of radionuclides. The heat treatment of spent titanium phosphate sorbent with the molar ratio P: Ti(IV) ≤ 1 results in the formation of stable poorly soluble mineral-like crystalline matrices of framework structure with a low-mobility cationic sublattice. Immobilization of radionuclides directly in the spent titanium phosphate sorbent upon its conversion into the crystalline state in the form of a stable ceramic matrix allows minimization of the volume of waste to be disposed of and enhancement of the reliability of their long-term storage.



Measurement of the 137Cs concentration by its own β-radiation using liquid scintillation spectrometry
Abstract
The possibility of measuring the 137Cs concentration in seawater by its own β-radiation using liquid scintillation spectrometry after preliminary sorption on cellulose fiber impregnated with copper(II) ferrocyanide was studied. This measurement procedure allows the 137Cs detection efficiency to be increased to 50% and the sample volume to be decreased from 1000 (as in γ-ray spectrometry) to 50 L and less.



Synthesis of 177Lu-based bioconjugate for radioimmunotherapy and evaluation of its stability in physiological media
Abstract
Labeling of the conjugated molecule of human serum albumin (HSA) and humanized scFv 4D5 mini-antibody specific to her-2/neu receptor with β-emitting 177Lu radionuclide via p-SCN-benzyl-DTPA chelator was studied. The radioconjugate can be prepared with the decay-corrected radiochemical yield of 82%. The stability of the synthesized complex in physiological solutions (normal saline, human blood serum) was evaluated. The complex is stable in physiological solutions for no less than 10 days.



Preparation and quality control of 32P-labeled albumin particles for internal radiotherapy
Abstract
The paper deals with the preparation and quality control of 32P-labeled albumin particles used in therapy of inoperable solid tumors with remarkable vascularization. A process was developed for preparing 32P-labeled albumin particles by combining biocompatible human serum albumin and [32P]phosphoric acid salt. Factors affecting the process were investigated, and labeling conditions were optimized. The size distribution, shape, and radiochemical stability of particles were determined. The biodistribution of the particles was examined after intravenous injection in Wistar rats. The in vivo stability and distribution of the radioactive particles in mice were studied with different administration methods. Optical microscopic examinations revealed that the particles had a narrow size distribution (20–50 μm) after sterilization and dispersion in a mixture of normal saline and human serum albumin or in Tween 80 solution. The particles prepared had high radiochemical stability and 99% purity. Experiments on the distribution in animals showed that high radioactivity was accumulated in the lungs as a vascular tumor model.



Effect of γ-irradiation on the thermal decomposition of nitric acid saturated solutions of TBP in С13 diluent
Abstract
The dynamics of gas evolution in the course of thermal oxidation of 30% solutions of tri-n-butyl phosphate (TBP) in C13 diluent, equilibrated with 12.9 M HNO3, was studied in open vessels in the temperature interval from 70 to 150°С. The total volumes of the released gases were measured, and the effect of the preliminary γ-irradiation of the TBP–С13–HNO3 system on the thermolysis of nitric acid and accumulation of liquid products of TBP decomposition was studied. The boundary temperature parameters for the development of the oxidation process in the autocatalytic mode were estimated. On heating of the single-phase systems in open vessels, the conditions for the development of the autocatalytic oxidation are not created.



α-Radiolysis of the tributyl phosphate–hydrocarbon diluent–nitric acid system
Abstract
α-Radiolysis of tributyl phosphate in Sintin n-paraffin diluent in equilibrium with HNO3 solutions at single “internal” irradiation from the extracted 238Pu was studied. The radiation-chemical yields (molecules/100 eV) of butyl hydrogen phosphates (BHP), carboxylic acids, carbonyl compounds, and nitro compounds upon irradiation of 20% TBP in the treated Sintin in equilibrium with 3 M HNO3 were 0.4 (at dibutyl hydrogen phosphate to monobutyl dihydrogen phosphate ratio HDBP: H2MBP = 4.3), 1.4, 0.2–0.3, and 0.2–0.3, respectively. The degradation and oxidation processes occur more deeply than under γ-irradiation. A simple volumetric method for determining carboxylic acids in the extract was developed. In the course of irradiation, the Pu(IV) oxidation state in the extract does not change, and its retention is due to the interaction with BHP at the ratio BHP: Pu = 2 in stripping with 0.02 M HNO3 and BHP: Pu = 4 in stripping with Fe(II). The retention can be eliminated by the displacing action of Np(IV).



Structure and hydrolytic durability of a glass containing waste from spent tributyl phosphate reprocessing
Abstract
The structure of the glass obtained by incorporation of the residue from reprocessing of the spent extractant, tributyl phosphate, into sodium aluminophosphate glass and the structural state of uranium in this glass were studied by vibration (IR, Raman) and X-ray absorption (XAFS) spectroscopy. An IR and Raman spectroscopic study shows that the structural network of the glasses is formed by ortho- and pyrophosphate groups linked by tetrahedral AlO4 units. As follows from the XAFS data, uranium is present in the glass in the form of uranyl ions and of separate UO2+x particles. The glass has high hydrolytic durability: The uranium leach rate determined in accordance with GOST (State Standard) R 52 126–2003 is of the order of 10–8 g cm–2 day–1.



Borobasalt systems as host materials for incorporation of radioactive waste from pyroelectrochemical technology
Abstract
Borobasalt systems were studied as host materials for incorporation of radioactive waste from pyroelectrochemical technology. For all the examined compositions, the leach rates are of the order of 10–7 g cm–2 day–1, which is quite acceptable for radionuclide immobilization. The synthesis temperature ensuring formation of homogeneous glasses is about 1250°С for all the examined compositions. The host material is capable to incorporate up to 40 wt % phosphate wastes, which seems quite sufficient from the viewpoint of technology. The system is only weakly sensitive to variations of the boric anhydride content.



Determination of the major, minor, and trace element mass fractions in Iranian cement by INAA and WDXRF
Abstract
The elemental composition of three different Iranian cement samples was determined by instrumental neutron activation analysis with the aim of quality control. The mass fractions for 4 major (Ca, Si, Fe, Al) and the 21 minor and trace elements (Mg, V, Mn, Na, As, La, Sb, Sm, U, Ba, Ce, Co, Cr, Eu, Hf, Sc, Sr, Th, Zn, S, K) were determined. X-ray fluorescence analysis was also used. The results obtained by both methods for Na, Mg, Fe, Ca, and Al are in good agreement. On the whole, the Iranian cement quality is quite acceptable according to national and international standards.


