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Evaluation of the Effect of External and Internal Irradiation on the Properties of Vitrified HLW to Substantiate the Safety of Their Environmental Impact 评价外部和内部辐照对玻璃化高放废物特性的影响以证实其环境影响的安全性
IF 0.9 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-10-06 DOI: 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.

报告了在研究外部质子辐照对模拟硼硅酸盐和铝磷酸盐玻璃的特性和结构的影响以及内部辐照对玛雅克生产协会放射化学工厂储存库中的活性玻璃的影响的初始阶段所取得的结果。这些结果表明,马雅克生产协会使用的玻璃熔化技术能够可靠地确保含有高放射性废物的玻璃的环境安全。
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引用次数: 0
Influence of Ionizıng Radiation on Physicochemical and Operational Properties of Diesel Fuel with Added Toluene 电离辐射对添加甲苯的柴油的物理化学和操作特性的影响
IF 0.9 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-10-06 DOI: 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。
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引用次数: 0
Treatment of Crude Phosphoric Acid Using Activated Carbon-Based Nanocomposites Integrated with Catalytic Wet Peroxide Oxidation 利用活性碳基纳米复合材料与催化湿式过氧化物氧化相结合处理粗磷酸
IF 0.9 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-10-06 DOI: 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。
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引用次数: 0
Determination of 239,240Pu in Caspian Sea Water Using the Sorption–Diffusion Model of the Radionuclide Uptake by Bottom Sediments 利用底层沉积物吸收放射性核素的吸附-扩散模型测定里海海水中的 239,240Pu
IF 0.9 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-10-06 DOI: 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.

里海海水中 239,240Pu 的全球含量(1996-2056 年)是利用底层沉积物吸收放射性核素的吸附-扩散模型计算得出的,其分布系数 Kd = 50 × 103,扩散系数 D = 0.1 × 10-7 cm2/s。假设 239、240Pu 在海洋上的全球沉降量等于俄罗斯中纬度地带的实验值 60 Bq/m2。按照海面上 58 Bq/m2 的钚沉降物密度计算,截至 1964 年,Q 海洋中的钚存量为 21.9 TBq。1996 年,实验测定的 239,240Pu 在里海海水中的浓度约为 20 μBq/L,模型计算得出的浓度为 17.8 μBq/L。在全球 239,240Pu 约 30 年的迁移过程中,约 93% 的放射性核素从水相转移到了底层土壤。根据计算结果,1996-2056 年期间海水中的 239,240Pu 浓度将从 17.8 μBq/L 降至 10.5 μBq/L,海水中的 239,240Pu 存量将从放射性尘降值的 6.3% 降至 3.7%。利用一种独立的方法对里海海水中的 90Sr 进行了监测,并确定了海水中 239,240Pu/90Sr 的浓度比,从而验证了上述结果。通过这两种方法估算海水中 239、240Pu 浓度(2017-2020 年)的结果相互吻合。
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引用次数: 0
Determination of 137Cs in Natural Water and Waste Streams Using Ferrocyanide Sorbents Based on Various Supports: a Comparative Analysis 使用基于各种支持物的亚铁氰化物吸附剂测定天然水和废水中的 137Cs:对比分析
IF 0.9 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-10-06 DOI: 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.

研究了在天然水和废水 137Cs 测定法中使用亚铁氰化物吸附剂 NPF-HTD、NPF-C 和 T-35 进行铯浓缩的可能性。结果表明,吸附剂的吸附特性和浓缩物中铯的化学收率达到 98-99% 的条件存在差异。考虑到样品体积与吸附剂在色谱柱中的质量之比、137Cs 的检测效率以及浓缩物测量时间,以达到样品中 137Cs 的最低可检测活度为 0.001-0.01 Bq/L,开发了一种测定天然水和废水中 137Cs 的可变方法。该方法已在斯维尔德洛夫斯克州和车里雅宾斯克州境内的天然水库和河流水域以及长期储存和处理放射性废物地区的监测井水中进行了 137Cs 检测试验。文中提供了有关河水和水库水成分的数据,并说明了浓缩物中的铯化学产量与样本中大成分浓度的关系。
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引用次数: 0
Neptunium(VI) Nitrate Complexes with Urea and Terpyridine Derivatives 硝酸镎(VI)与尿素和特吡啶衍生物的络合物
IF 0.9 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-07-16 DOI: 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。
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引用次数: 0
Structure and IR Spectroscopic Study of Sodium Tris(monoiodacetato)uranilate 三(单碘乙酰氧基)尿酸钠的结构和红外光谱研究
IF 0.9 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-07-16 DOI: 10.1134/S1066362224030020
V. N. Serezhkin, M. S. Grigoriev, D. S. Mitinа, V. Yu. Losev, L. B. Serezhkina

NaUO2(mia)3 (I) crystals (mia: monoiodacetate ion CH2ICOO) were synthesized and studied by X-ray diffraction and IR spectroscopic analyses. Uranyl-containing complexes [UO2(mia)3] in the structure correspond to the crystal chemical formula A(B01)3, where A = UO22+, B01 = mia. Using coordination sequences, we analyzed the features of the 3D framework, which is realized in the structure of crystals of I and contains 8 crystallographically nonequivalent U or Na atoms. A semiempirical calculation and comparison of the calculated and experimental vibration frequencies in the IR spectrum of I were performed.

摘要 合成了 NaUO2(mia)3 (I) 晶体(mia:单碘乙酸根离子 CH2ICOO-),并通过 X 射线衍射和红外光谱分析对其进行了研究。含铀配合物 [UO2(mia)3]- 的结构对应于晶体化学式 A(B01)3,其中 A = UO22+,B01 = mia。我们利用配位序列分析了三维框架的特征,该框架是在 I 晶体结构中实现的,包含 8 个晶体学上不等价的 U 原子或 Na 原子。我们进行了半经验计算,并比较了 I 的红外光谱中的计算振动频率和实验振动频率。
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引用次数: 0
Production of 105Rh Using Electron Accelerators and a New Method for Its Recovery from Irradiated Targets 利用电子加速器生产 105Rh 以及从辐照靶中回收 105Rh 的新方法
IF 0.9 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-07-16 DOI: 10.1134/S1066362224030093
A. G. Kazakov, J. S. Babenya, T. Y. Ekatova, E. Y. Khvorostinin, S. S. Belyshev, A. A. Kuznetsov, V. V. Khankin, S. E. Vinokurov, B. F. Myasoedov

105Rh is one of the promising beta-emitters for therapeutic purposes in nuclear medicine, but its use is limited, due to in part its low availability, which dictates the search for new effective ways to produce it. In this work, the radionuclide composition of a PdCl2 target irradiated by bremsstrahlung photons is determined and a method is proposed for recovery carrier free 105Rh from it using a commercial DGA sorbent, which ensures a high degree of purification of the target isotope. In future, the studies carried out may contribute to the practical application of 105Rh to nuclear medicine.

摘要 105Rh 是核医学中很有希望用于治疗目的的β发射体之一,但其使用受到限制,部分原因是其可用性较低,这就要求寻找新的有效方法来生产它。在这项工作中,确定了轫致辐射光子照射下的氯化钯靶的放射性核素组成,并提出了一种使用商用 DGA 吸附剂从中回收游离载流子 105Rh 的方法,该方法可确保靶同位素的高度纯化。今后,所进行的研究可能有助于 105Rh 在核医学中的实际应用。
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引用次数: 0
Hydrogen Peroxide in the Chemistry of f-Elements f 元素化学中的过氧化氢
IF 0.9 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-07-16 DOI: 10.1134/S1066362224030019
V. P. Shilov, A. M. Fedoseev, B. F. Myasoedov

The properties of H2O2 and its reactions with lanthanide and actinide ions are considered. The potential values of pairs involving H2O2 in acidic and alkaline solutions are given. Depending on the oxidative potential of the f-element ion and pH, H2O2 exhibits oxidizing or reducing properties. The kinetics and mechanisms of reactions of H2O2 with lanthanides(II–IV) and with actinides(III–VII) in acidic, carbonate, and alkaline media have been analyzed. Ions of f-elements(III–VI) form peroxide complexes. The peroxo group occupies either one (OOH) or two (OO) coordination sites. U(VI), Np(IV) binds up to 3 peroxo groups. Oxidation or reduction reactions proceed intramolecularly. In the case of Yb2+, Sm2+, U3+, Ce4+ (in an acid solution), Pr(IV) and Am(IV) (in a weakly acidic medium), the bimolecular rate constants are 105n × 106 L/(mol s), which exceeds the rate of ligand exchange in the coordination sphere of the f-element ion. Therefore, charge transfer occurs in the outer sphere. Coordination spheres of Ce(IV) oxalate, Tb(IV) with P2W17O6110–, and Np(VI) with NO3 slow down the charge transfer between H2O2 and the f-element ion. H2O2 arising during the radiolysis of aqueous solutions is in an excited state and is more active than H2O2 introduced from the outside. Of particular interest are the reactions of H2O2 with ions of f-elements in strongly complexing or nonaqueous (organic) media, as well as structural studies of solid compounds of peroxides of f-elements.

摘要 研究了 H2O2 的性质及其与镧系离子和锕系离子的反应。给出了在酸性和碱性溶液中涉及 H2O2 的对的电位值。根据 f 元素离子的氧化电位和 pH 值,H2O2 具有氧化性或还原性。分析了 H2O2 与镧系元素(II-IV)和锕系元素(III-VII)在酸性、碳酸盐和碱性介质中反应的动力学和机理。f 元素(III-VI)的离子形成过氧化物络合物。过氧基团占据一个(OOH)或两个(OO)配位位点。U(VI)、Np(IV)最多可结合 3 个过氧基团。氧化或还原反应在分子内进行。对于 Yb2+、Sm2+、U3+、Ce4+(在酸性溶液中)、Pr(IV) 和 Am(IV)(在弱酸性介质中),双分子速率常数为 105-n × 106 L/(mol s),超过了 f 元素离子配位层中配体交换的速率。因此,电荷转移发生在外配位层。草酸 Ce(IV)、P2W17O6110- Tb(IV)和 NO3- Np(VI)的配位球会减缓 H2O2 和 f 元素离子之间的电荷转移。在水溶液的辐射分解过程中产生的 H2O2 处于激发态,比从外部引入的 H2O2 更活跃。特别令人感兴趣的是 H2O2 与 f 元素离子在强络合或非水(有机)介质中的反应,以及 f 元素过氧化物固体化合物的结构研究。
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引用次数: 0
Features of the Sorption Interaction of [3H]Hyaluronic Acid with Hydroxyapatite 3H]透明质酸与羟基磷灰石的吸附相互作用特征
IF 0.9 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-07-16 DOI: 10.1134/S106636222403010X
G. A. Badun, A. V. Severin, E. A. Zaitseva

[3H]Hyaluronic acid with a molecular weight of 2.37 MDa and a specific radioactivity of 35 GBq/g was obtained using the tritium thermal activation method. Tritium labeled hyaluronic acid (HA) with a molecular weight of 2.37, 0.20, and 0.10 MDa were used to study their adsorption on hydroxyapatite (HAP) in two textural modifications: aqueous suspension and powder. Differences in adsorption kinetics and adsorption isotherms were observed due to variations in the interaction between polysaccharide molecules and the sorbent forms under consideration. The adsorption isotherms of HA on HAP were proven linear. It is shown that strong HA–HAP complexes are formed, and no desorption of HA into water and 0.9% NaCl solution were detected in 2 days.

摘要 利用氚热活化法获得了分子量为 2.37 MDa、比放射性为 35 GBq/g 的[3H]透明质酸。研究了分子量分别为 2.37、0.20 和 0.10 MDa 的氚标记透明质酸(HA)在水悬浮液和粉末两种质地的羟基磷灰石(HAP)上的吸附情况。由于多糖分子与所考虑的吸附剂形式之间的相互作用存在差异,因此在吸附动力学和吸附等温线方面也出现了差异。事实证明,HA 对 HAP 的吸附等温线呈线性关系。结果表明,HA-HAP 形成了很强的复合物,而且在 2 天内没有发现 HA 解吸到水和 0.9% 氯化钠溶液中。
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引用次数: 0
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Radiochemistry
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