Pub Date : 2024-10-06DOI: 10.1134/S1066362224040143
A. E. Miroslavov, P. M. Kuz’menko, M. Yu. Tyupina, A. P. Sakhonenkova, G. V. Sidorenko, A. R. Kochergina, S. A. Krotov
A novel 12-step procedure was developed for preparing methyl 14-isocyano-3-methyltetradecanoate. “2+1B” tricarbonyl complexes [99mTc(CO)3(N^N)CN(CH2)11CH(CH3)CH2COOMe]+, where N^N = 2,2'-bipyridine (bipy) or 1,10-phenanthroline (phen), were prepared by the reaction of [99mTc(CO)3(N^N)(H2O,EtOH)]+ with methyl 14-isocyano-3-methyltetradecanoate in aqueous ethanol. The formation of technetium-99m complexes was confirmed by HPLC, and the partition coefficient (n-octanol/water) of these complexes was measured.
{"title":"“2+1B” Technetium-99m Tricarbonyl Complexes with N,N'-Bidentate Ligands and Methyl 14-Isocyano-3-methyltetradecanoate","authors":"A. E. Miroslavov, P. M. Kuz’menko, M. Yu. Tyupina, A. P. Sakhonenkova, G. V. Sidorenko, A. R. Kochergina, S. A. Krotov","doi":"10.1134/S1066362224040143","DOIUrl":"10.1134/S1066362224040143","url":null,"abstract":"<p>A novel 12-step procedure was developed for preparing methyl 14-isocyano-3-methyltetradecanoate. “2+1<sub>B</sub>” tricarbonyl complexes [<sup>99<i>m</i></sup>Tc(CO)<sub>3</sub>(N^N)CN(CH<sub>2</sub>)<sub>11</sub>CH(CH<sub>3</sub>)CH<sub>2</sub>COOMe]<sup>+</sup>, where N^N = 2,2'-bipyridine (bipy) or 1,10-phenanthroline (phen), were prepared by the reaction of [<sup>99<i>m</i></sup>Tc(CO)<sub>3</sub>(N^N)(H<sub>2</sub>O,EtOH)]<sup>+</sup> with methyl 14-isocyano-3-methyltetradecanoate in aqueous ethanol. The formation of technetium-99<i>m</i> complexes was confirmed by HPLC, and the partition coefficient (<i>n</i>-octanol/water) of these complexes was measured.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 4","pages":"522 - 530"},"PeriodicalIF":0.9,"publicationDate":"2024-10-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142410262","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-06DOI: 10.1134/S1066362224040015
L. B. Serezhkina, M. S. Grigoriev, D. S. Mitinа, V. N. Serezhkin
Synthesis, IR spectroscopic, and X-ray diffraction studies of R[UO2(mia)3]2·2Hmia·4H2O crystals, where R = Sr2+ (I) or Ba2+ (II), and mia is the monoiodacetate ion CH2ICOO−, have been carried out. The [UO2(mia)3]– complexes correspond to the crystal chemical formula A(B01)3, where A = UO22+, B01 = mia. It has been established that a common feature of I and II is the presence of trinuclear electrically neutral clusters {R[UO2(mia)3]2(Hmia)2(H2O)2}. At the centers of the clusters there are trigonal RO8 dodecahedra; half of their oxygen atoms belong to four different mia anions of two [UO2(mia)3]– complexes. In addition, each R atom coordinates the oxygen atoms of two water molecules and the carbonyl oxygen atoms of two Hmia molecules. Using the method of molecular Voronoi–Dirichlet polyhedra, an analysis of noncovalent interactions in the structure of I was carried out.
对 R[UO2(mia)3]2-2Hmia-4H2O 晶体(其中 R = Sr2+ (I) 或 Ba2+ (II),mia 为单碘乙酸根离子 CH2ICOO-)进行了合成、红外光谱和 X 射线衍射研究。UO2(mia)3]- 复合物的晶体化学式为 A(B01)3,其中 A = UO22+,B01 = mia。已确定 I 和 II 的共同特征是存在三核电中性簇{R[UO2(mia)3]2(Hmia)2(H2O)2}。簇的中心是 RO8 十二面体三面体;其中一半的氧原子属于两个[UO2(mia)3]- 复合物的四个不同的 mia 阴离子。此外,每个 R 原子还与两个水分子的氧原子和两个 Hmia 分子的羰基氧原子配位。利用分子 Voronoi-Dirichlet 多面体的方法,对 I 结构中的非共价相互作用进行了分析。
{"title":"Crystal Structure of New Iodacetatouranylates R[UO2(CH2ICOO)3]2·2CH2ICOOH·4H2O (R = Sr or Ba)","authors":"L. B. Serezhkina, M. S. Grigoriev, D. S. Mitinа, V. N. Serezhkin","doi":"10.1134/S1066362224040015","DOIUrl":"10.1134/S1066362224040015","url":null,"abstract":"<p>Synthesis, IR spectroscopic, and X-ray diffraction studies of R[UO<sub>2</sub>(mia)<sub>3</sub>]<sub>2</sub>·2Hmia·4H<sub>2</sub>O crystals, where R = Sr<sup>2+</sup> (<b>I</b>) or Ba<sup>2+</sup> (<b>II</b>), and mia is the monoiodacetate ion CH<sub>2</sub>ICOO<sup>−</sup>, have been carried out. The [UO<sub>2</sub>(mia)<sub>3</sub>]<sup>–</sup> complexes correspond to the crystal chemical formula A(B<sup>01</sup>)<sub>3</sub>, where A = UO<sub>2</sub><sup>2+</sup>, B<sup>01</sup> = mia. It has been established that a common feature of <b>I</b> and <b>II</b> is the presence of trinuclear electrically neutral clusters {R[UO<sub>2</sub>(mia)<sub>3</sub>]<sub>2</sub>(Hmia)<sub>2</sub>(H<sub>2</sub>O)<sub>2</sub>}. At the centers of the clusters there are trigonal RO<sub>8</sub> dodecahedra; half of their oxygen atoms belong to four different mia anions of two [UO<sub>2</sub>(mia)<sub>3</sub>]<sup>–</sup> complexes. In addition, each R atom coordinates the oxygen atoms of two water molecules and the carbonyl oxygen atoms of two Hmia molecules. Using the method of molecular Voronoi–Dirichlet polyhedra, an analysis of noncovalent interactions in the structure of <b>I</b> was carried out.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 4","pages":"397 - 404"},"PeriodicalIF":0.9,"publicationDate":"2024-10-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142410220","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-06DOI: 10.1134/S1066362224040052
A. N. Turanov, V. K. Karandashev, V. E. Baulin, D. V. Baulin
The effect of the ionic liquid, 1-butyl-3-methylimidazolium bis[(trifluoromethyl)sulfonyl]imide, on the extraction of lanthanides(III) from nitric acid solutions with phosphoryl-containing podands (2-(2-diphenylphosphoryl)-4-ethylphenoxy)methyl)diphenylphosphine oxide (1), (2-(2-diphenylphosphoryl)-4-ethylphenoxy)ethyl)diphenylphosphine oxide (2), and 2-[2-(diphenylphosphoryl)-4-ethylphenoxy]-N,N-dioctylacetamide (3) was studied. The stoichiometry of the extracted complexes was determined. The efficiency of extraction of lanthanides(III) with solutions of compounds 1–3 in dichloroethane from nitric acid solutions increases in the order 3 < 2 < 1. It has been established that, when replacing dichloroethane with an ionic liquid as a diluent, the extraction efficiency enhances. The magnitude of this effect decreases in the series of compounds 3 > 2 > 1. In the case of compound 1, the replacement of dichloroethane with an ionic liquid as a solvent is accompanied by a decrease in the extraction of lanthanides(III) at [HNO3] > 1.5 M.
{"title":"Effect of Ionic Liquid on the Extraction of Lanthanides(III) from Nitric Acid Solutions with Phosphoryl-Containing Podands","authors":"A. N. Turanov, V. K. Karandashev, V. E. Baulin, D. V. Baulin","doi":"10.1134/S1066362224040052","DOIUrl":"10.1134/S1066362224040052","url":null,"abstract":"<p>The effect of the ionic liquid, 1-butyl-3-methylimidazolium bis[(trifluoromethyl)sulfonyl]imide, on the extraction of lanthanides(III) from nitric acid solutions with phosphoryl-containing podands (2-(2-diphenylphosphoryl)-4-ethylphenoxy)methyl)diphenylphosphine oxide (<b>1</b>), (2-(2-diphenylphosphoryl)-4-ethylphenoxy)ethyl)diphenylphosphine oxide (<b>2</b>), and 2-[2-(diphenylphosphoryl)-4-ethylphenoxy]-<i>N,N</i>-dioctylacetamide (<b>3</b>) was studied. The stoichiometry of the extracted complexes was determined. The efficiency of extraction of lanthanides(III) with solutions of compounds <b>1–3</b> in dichloroethane from nitric acid solutions increases in the order 3 < 2 < 1. It has been established that, when replacing dichloroethane with an ionic liquid as a diluent, the extraction efficiency enhances. The magnitude of this effect decreases in the series of compounds <b>3</b> > <b>2</b> > <b>1</b>. In the case of compound <b>1</b>, the replacement of dichloroethane with an ionic liquid as a solvent is accompanied by a decrease in the extraction of lanthanides(III) at [HNO<sub>3</sub>] > 1.5 M.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 4","pages":"438 - 443"},"PeriodicalIF":0.9,"publicationDate":"2024-10-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142410265","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-06DOI: 10.1134/S1066362224040131
G. A. Badun, E. M. Zhidkova, M. G. Chernysheva, A. D. Enikeev, M. G. Yakubovskaya, E. A. Lesovaya
The possibility of introducing tritium into dexamethasone and dexamethasone phosphate using the thermal activation method was demonstrated. The affinity of ligands for glucocorticoid receptors has been successfully assessed using labeled compounds.
{"title":"Preparation of Tritium Labeled Dexamethasone Phosphate and Its Application to Assess the Affinity of Ligands for Glucocorticoid Receptors","authors":"G. A. Badun, E. M. Zhidkova, M. G. Chernysheva, A. D. Enikeev, M. G. Yakubovskaya, E. A. Lesovaya","doi":"10.1134/S1066362224040131","DOIUrl":"10.1134/S1066362224040131","url":null,"abstract":"<p>The possibility of introducing tritium into dexamethasone and dexamethasone phosphate using the thermal activation method was demonstrated. The affinity of ligands for glucocorticoid receptors has been successfully assessed using labeled compounds.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 4","pages":"514 - 521"},"PeriodicalIF":0.9,"publicationDate":"2024-10-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142410299","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-06DOI: 10.1134/S1066362224040167
N. P. Starovoitov, P. V. Kozlov, I. G. Tananaev, E. S. Braichun, N. A. Stakanova, M. B. Remizov, V. A. Dudkin, V. A. Kazakov, S. V. Korenev, E. V. Polyakov, N. V. Glushkova, E. A. Kinev, S. S. Zyryanov, M. N. Sarychev, A. V. Vasil’ev
The results obtained in the initial step of studying the effect of external proton irradiation on the properties and structure of simulated borosilicate and aluminophosphate glasses and of internal irradiation on the active glass arranged in the repository of the radiochemical plant of the Mayak Production Association are reported. These results show that the glass melting technologies used at the Mayak Production Association can reliably ensure the environmental safety of the glass incorporating the high-level waste.
{"title":"Evaluation of the Effect of External and Internal Irradiation on the Properties of Vitrified HLW to Substantiate the Safety of Their Environmental Impact","authors":"N. P. Starovoitov, P. V. Kozlov, I. G. Tananaev, E. S. Braichun, N. A. Stakanova, M. B. Remizov, V. A. Dudkin, V. A. Kazakov, S. V. Korenev, E. V. Polyakov, N. V. Glushkova, E. A. Kinev, S. S. Zyryanov, M. N. Sarychev, A. V. Vasil’ev","doi":"10.1134/S1066362224040167","DOIUrl":"10.1134/S1066362224040167","url":null,"abstract":"<p>The results obtained in the initial step of studying the effect of external proton irradiation on the properties and structure of simulated borosilicate and aluminophosphate glasses and of internal irradiation on the active glass arranged in the repository of the radiochemical plant of the Mayak Production Association are reported. These results show that the glass melting technologies used at the Mayak Production Association can reliably ensure the environmental safety of the glass incorporating the high-level waste.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 4","pages":"542 - 556"},"PeriodicalIF":0.9,"publicationDate":"2024-10-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142410226","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-06DOI: 10.1134/S1066362224040155
L. Y. Jabbarova, I. I. Mustafaev, A. S. Mirzaeva, N. A. Ibadov
Radiation resistance of diesel fuel with the addition of various percentages of toluene was studied. The experiments were carried out for a long time to study the postpolymerization processes. The kinetics of processes during irradiation of pure diesel fuel was studied at the temperature T = 20°C and dose rate P = 0.07 Gy/s in the range of absorbed doses D = 15–150 kGy, and a mixture of toluene with diesel fuel was irradiated within the absorbed dose range D = 24–90 kGy at a toluene concentration of 1, 3, and 5 vol %. Analysis by gas chromatography–mass spectrometric (GC/MS) was performed, and the density, viscosity, and iodine number of the diesel fuel before and after irradiation at various absorbed doses were determined. The kinetics of postpolymerization processes after the end of irradiation shows that the rate of the process and its share in the total polymerization depend on the irradiation time, initial mixture density, and dose. By adding additives (antirads), one can choose the composition of diesel fuel that will better withstand radiation exposure. It is necessary to find the optimal concentration of toluene in the composition of diesel fuel, at which the viscosity and density will not change with an increase in the absorbed dose.
研究了添加不同比例甲苯的柴油的抗辐射性。实验进行了很长时间,以研究后聚合过程。在温度 T = 20°C 和剂量率 P = 0.07 Gy/s 的吸收剂量 D = 15-150 kGy 的范围内,研究了纯柴油在辐照过程中的动力学过程;在甲苯浓度为 1、3 和 5 Vol % 的吸收剂量 D = 24-90 kGy 的范围内,研究了甲苯与柴油的混合物在辐照过程中的动力学过程。采用气相色谱-质谱法(GC/MS)进行了分析,并测定了在不同吸收剂量下辐照前后柴油的密度、粘度和碘值。辐照结束后的后聚合过程动力学表明,该过程的速率及其在总聚合中的比例取决于辐照时间、初始混合物密度和剂量。通过添加添加剂(抗辐照剂),可以选择更能承受辐照的柴油成分。必须找到柴油成分中甲苯的最佳浓度,在此浓度下,粘度和密度不会随着吸收剂量的增加而改变。
{"title":"Influence of Ionizıng Radiation on Physicochemical and Operational Properties of Diesel Fuel with Added Toluene","authors":"L. Y. Jabbarova, I. I. Mustafaev, A. S. Mirzaeva, N. A. Ibadov","doi":"10.1134/S1066362224040155","DOIUrl":"10.1134/S1066362224040155","url":null,"abstract":"<p>Radiation resistance of diesel fuel with the addition of various percentages of toluene was studied. The experiments were carried out for a long time to study the postpolymerization processes. The kinetics of processes during irradiation of pure diesel fuel was studied at the temperature <i>T</i> = 20°C and dose rate <i>P</i> = 0.07 Gy/s in the range of absorbed doses <i>D</i> = 15–150 kGy, and a mixture of toluene with diesel fuel was irradiated within the absorbed dose range <i>D</i> = 24–90 kGy at a toluene concentration of 1, 3, and 5 vol %. Analysis by gas chromatography–mass spectrometric (GC/MS) was performed, and the density, viscosity, and iodine number of the diesel fuel before and after irradiation at various absorbed doses were determined. The kinetics of postpolymerization processes after the end of irradiation shows that the rate of the process and its share in the total polymerization depend on the irradiation time, initial mixture density, and dose. By adding additives (antirads), one can choose the composition of diesel fuel that will better withstand radiation exposure. It is necessary to find the optimal concentration of toluene in the composition of diesel fuel, at which the viscosity and density will not change with an increase in the absorbed dose.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 4","pages":"531 - 541"},"PeriodicalIF":0.9,"publicationDate":"2024-10-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142410227","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-06DOI: 10.1134/S1066362224040064
M. N. Kouraim
Activated carbon (AC) decorated by silver (Ag/AC) and silica (Ag-Si/AC) nanoparticles was used in the treatment of crude phosphoric acid to remove some inorganic and organic impurities. The effect of time, solid/liquid ratio, temperature, and hydrogen peroxide dose on the phosphoric acid treatment was examined. The catalytic activity and uranium uptake efficiency are improved when carbon structures contain Ag and Si nanoparticles. Uranium and organic matter are removed from crude phosphoric acid more efficiently when crude phosphoric acid is treated with activated carbon decorated by silver (Ag/AC) and silica (Ag-Si/AC) nanoparticles with catalytic wet peroxide oxidation, compared to the treatment with activated carbon only, and at high acid concentration (8 M) and solid/liquid mass ratios (0.001), using unsurpassed H2O2. The higher removal efficiencies of uranium and organic matter (OM) were attributed to the increased adsorptive interactions between the AC-based adsorbent surfaces and the OM and uranium species.
银(Ag/AC)和二氧化硅(Ag-Si/AC)纳米颗粒装饰的活性炭(AC)被用于处理粗磷酸,以去除一些无机和有机杂质。研究了时间、固液比、温度和过氧化氢剂量对磷酸处理的影响。当碳结构中含有 Ag 和 Si 纳米颗粒时,催化活性和铀吸收效率都会提高。在高酸浓度(8 M)和固/液质量比(0.001)的条件下,与仅使用活性炭处理相比,使用银(Ag/AC)和硅(Ag-Si/AC)纳米颗粒装饰的活性炭处理粗磷酸,并使用无与伦比的过氧化氢进行催化湿氧化,能更有效地去除粗磷酸中的铀和有机物。铀和有机物(OM)的去除率较高的原因是基于 AC 的吸附剂表面与 OM 和铀物种之间的吸附相互作用增强了。
{"title":"Treatment of Crude Phosphoric Acid Using Activated Carbon-Based Nanocomposites Integrated with Catalytic Wet Peroxide Oxidation","authors":"M. N. Kouraim","doi":"10.1134/S1066362224040064","DOIUrl":"10.1134/S1066362224040064","url":null,"abstract":"<p>Activated carbon (AC) decorated by silver (Ag/AC) and silica (Ag-Si/AC) nanoparticles was used in the treatment of crude phosphoric acid to remove some inorganic and organic impurities. The effect of time, solid/liquid ratio, temperature, and hydrogen peroxide dose on the phosphoric acid treatment was examined. The catalytic activity and uranium uptake efficiency are improved when carbon structures contain Ag and Si nanoparticles. Uranium and organic matter are removed from crude phosphoric acid more efficiently when crude phosphoric acid is treated with activated carbon decorated by silver (Ag/AC) and silica (Ag-Si/AC) nanoparticles with catalytic wet peroxide oxidation, compared to the treatment with activated carbon only, and at high acid concentration (8 M) and solid/liquid mass ratios (0.001), using unsurpassed H<sub>2</sub>O<sub>2</sub>. The higher removal efficiencies of uranium and organic matter (OM) were attributed to the increased adsorptive interactions between the AC-based adsorbent surfaces and the OM and uranium species.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 4","pages":"444 - 453"},"PeriodicalIF":0.9,"publicationDate":"2024-10-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142410260","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-06DOI: 10.1134/S1066362224040180
N. A. Bakunov, A. O. Aksenov
The content of global 239,240Pu in Caspian sea water (1996–2056) was calculated using the sorption–diffusion model of the radionuclide uptake by bottom sediments with the distribution coefficient Kd = 50 × 103 and diffusion coefficient D = 0.1 × 10–7 cm2/s. The 239,240Pu global fallout on the sea was assumed to be equal to the experimental value for the mid-latitude belt of Russia, 60 Bq/m2. At the plutonium fallout density on the sea surface of 58 Bq/m2, its inventory in the sea Q as of the year 1964 is 21.9 TBq. In 1996, the experimentally determined 239,240Pu concentration in Caspian sea water was ~20 μBq/L, and the calculation by the model gives 17.8 μBq/L. During the ~30-year migration of global 239,240Pu, about 93% of the radionuclide passed from the aqueous phase to bottom soils. According to the calculations, the 239,240Pu concentration in the seawater in the period 1996–2056 will decrease from 17.8 to 10.5 μBq/L, and the 239,240Pu inventory in the seawater, from 6.3 to 3.7%, of the fallout value. The results were verified using an independent method for 90Sr monitoring in Caspian sea water and determining the 239,240Pu/90Sr concentration ratio in the water. The results of estimating the 239,240Pu concentrations in the seawater (2017–2020) by these two methods reasonably agree with each other.
{"title":"Determination of 239,240Pu in Caspian Sea Water Using the Sorption–Diffusion Model of the Radionuclide Uptake by Bottom Sediments","authors":"N. A. Bakunov, A. O. Aksenov","doi":"10.1134/S1066362224040180","DOIUrl":"10.1134/S1066362224040180","url":null,"abstract":"<p>The content of global <sup>239,240</sup>Pu in Caspian sea water (1996–2056) was calculated using the sorption–diffusion model of the radionuclide uptake by bottom sediments with the distribution coefficient <i>K</i><sub>d</sub> = 50 × 10<sup>3</sup> and diffusion coefficient <i>D</i> = 0.1 × 10<sup>–7</sup> cm<sup>2</sup>/s. The <sup>239,240</sup>Pu global fallout on the sea was assumed to be equal to the experimental value for the mid-latitude belt of Russia, 60 Bq/m<sup>2</sup>. At the plutonium fallout density on the sea surface of 58 Bq/m<sup>2</sup>, its inventory in the sea <i>Q</i> as of the year 1964 is 21.9 TBq. In 1996, the experimentally determined <sup>239,240</sup>Pu concentration in Caspian sea water was ~20 μBq/L, and the calculation by the model gives 17.8 μBq/L. During the ~30-year migration of global <sup>239,240</sup>Pu, about 93% of the radionuclide passed from the aqueous phase to bottom soils. According to the calculations, the <sup>239,240</sup>Pu concentration in the seawater in the period 1996–2056 will decrease from 17.8 to 10.5 μBq/L, and the <sup>239,240</sup>Pu inventory in the seawater, from 6.3 to 3.7%, of the fallout value. The results were verified using an independent method for <sup>90</sup>Sr monitoring in Caspian sea water and determining the <sup>239,240</sup>Pu/<sup>90</sup>Sr concentration ratio in the water. The results of estimating the <sup>239,240</sup>Pu concentrations in the seawater (2017–2020) by these two methods reasonably agree with each other.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 4","pages":"570 - 575"},"PeriodicalIF":0.9,"publicationDate":"2024-10-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142410261","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-06DOI: 10.1134/S1066362224040118
A. V. Voronina, A. K. Suetina
The possibility of using ferrocyanide sorbents NPF-HTD, NPF-C, and T-35 for cesium concentration in the method of 137Cs determination in natural and waste waters has been investigated. Differences in sorption characteristics of sorbents and conditions of cesium concentration to achieve a chemical yield of 98–99% in the concentrate have been revealed. A variable method for determination of 137Cs in natural and waste waters has been developed, taking into account the ratio of sample volume and sorbent mass in the column, the efficiency of 137Cs detection, and the time of concentrate measurement to achieve the minimum detectable activity of 137Cs in the sample of 0.001–0.01 Bq/L. The method was tested for determination of 137Cs in waters of natural reservoirs and rivers in the territories of Sverdlovsk oblast and Chelyabinsk oblast, as well as waters of monitoring wells in the territories of long-term storage and disposal of radioactive waste. The data on the composition of river and reservoir waters are presented, and the dependence of the cesium chemical yield into the concentrate on the concentration of macrocomponents in samples is shown.
{"title":"Determination of 137Cs in Natural Water and Waste Streams Using Ferrocyanide Sorbents Based on Various Supports: a Comparative Analysis","authors":"A. V. Voronina, A. K. Suetina","doi":"10.1134/S1066362224040118","DOIUrl":"10.1134/S1066362224040118","url":null,"abstract":"<p>The possibility of using ferrocyanide sorbents NPF-HTD, NPF-C, and T-35 for cesium concentration in the method of <sup>137</sup>Cs determination in natural and waste waters has been investigated. Differences in sorption characteristics of sorbents and conditions of cesium concentration to achieve a chemical yield of 98–99% in the concentrate have been revealed. A variable method for determination of <sup>137</sup>Cs in natural and waste waters has been developed, taking into account the ratio of sample volume and sorbent mass in the column, the efficiency of <sup>137</sup>Cs detection, and the time of concentrate measurement to achieve the minimum detectable activity of <sup>137</sup>Cs in the sample of 0.001–0.01 Bq/L. The method was tested for determination of <sup>137</sup>Cs in waters of natural reservoirs and rivers in the territories of Sverdlovsk oblast and Chelyabinsk oblast, as well as waters of monitoring wells in the territories of long-term storage and disposal of radioactive waste. The data on the composition of river and reservoir waters are presented, and the dependence of the cesium chemical yield into the concentrate on the concentration of macrocomponents in samples is shown.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 4","pages":"493 - 505"},"PeriodicalIF":0.9,"publicationDate":"2024-10-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142410325","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-07-16DOI: 10.1134/S1066362224030032
I. A. Charushnikova, M. S. Grigoriev, A.M. Fedoseev
Two new complex Np(VI) nitrates with carbamoylurea (biuret) and with a derivative of terpyridine (Ph-Terpy) of the composition [(NpO2)(biuret)(NO3)2] (I) and [H2(Ph-terpy)(NO3)]2[NpO2(NO3)4] (II) have been synthesized and structurally characterized. The coordination environment of Np atoms in compounds are distorted hexagonal bipyramids with “yl” oxygen atoms in apical positions. The equatorial plane of the bipyramid in complex I is formed by oxygen atoms of two bidentate NO3– anions and an electroneutral ligand. The equatorial plane of the bipyramid in II is formed by oxygen atoms of two bidentate and two monodentate NO3– anions. The twice protonated Ph-terpy is the basis of the complex cation [H2(Ph-terpy)(NO3)]+.
摘要 合成了两种新的络合物 Np(VI)硝酸盐,它们分别与氨基甲酰脲(biuret)和特吡啶(Ph-Terpy)的衍生物组成[(NpO2)(biuret)(NO3)2](I)和[H2(Ph-terpy)(NO3)]2[NpO2(NO3)4](II),并在结构上进行了表征。化合物中 Np 原子的配位环境是畸变的六角二棱锥,"yl "氧原子位于顶端位置。复合物 I 中双锥体的赤道面是由两个双齿 NO3- 阴离子的氧原子和一个电中性配体形成的。复合物 II 中双锥体的赤道面由两个双齿和两个单齿 NO3- 阴离子的氧原子构成。两次质子化的 Ph-terpy 是络合物阳离子 [H2(Ph-terpy)(NO3)]+ 的基础。
{"title":"Neptunium(VI) Nitrate Complexes with Urea and Terpyridine Derivatives","authors":"I. A. Charushnikova, M. S. Grigoriev, A.M. Fedoseev","doi":"10.1134/S1066362224030032","DOIUrl":"10.1134/S1066362224030032","url":null,"abstract":"<p>Two new complex Np(VI) nitrates with carbamoylurea (biuret) and with a derivative of terpyridine (Ph-Terpy) of the composition [(NpO<sub>2</sub>)(biuret)(NO<sub>3</sub>)<sub>2</sub>] (<b>I</b>) and [H<sub>2</sub>(Ph-terpy)(NO<sub>3</sub>)]<sub>2</sub>[NpO<sub>2</sub>(NO<sub>3</sub>)<sub>4</sub>] (<b>II</b>) have been synthesized and structurally characterized. The coordination environment of Np atoms in compounds are distorted hexagonal bipyramids with “yl” oxygen atoms in apical positions. The equatorial plane of the bipyramid in complex <b>I</b> is formed by oxygen atoms of two bidentate NO<sub>3</sub><sup>–</sup> anions and an electroneutral ligand. The equatorial plane of the bipyramid in <b>II</b> is formed by oxygen atoms of two bidentate and two monodentate NO<sub>3</sub><sup>–</sup> anions. The twice protonated Ph-terpy is the basis of the complex cation [H<sub>2</sub>(Ph-terpy)(NO<sub>3</sub>)]<sup>+</sup>.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 3","pages":"310 - 320"},"PeriodicalIF":0.9,"publicationDate":"2024-07-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141719659","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}