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Chemical and Radiochemical Analysis of the Spent Sorbent from Iodine Adsorption Columns of the Mayak PA RT Plant Mayak PA RT厂碘吸附柱废吸附剂的化学和放射化学分析
IF 1 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-10-13 DOI: 10.1134/S1066362225040149
Ye. V. Chukhlantseva, Yu. M. Tatarnikova, S. V. Stepanov, O. V. Stepanova, K. A. Dzhevello

Spent iodine-bearing sorbents accumulated at the Mayak Production Association were subjected to chemical and radiochemical analysis. The mass fractions of sorbent macrocomponents (Al, Ag, NO3, and total I) and related impurities (F, Cl, and SO42–) were measured. The total specific α- and β-activity, the specific activity of long-lived α- and β-emitting radionuclides whose identification was analytically possible (99Tc, U and Pu isotopes, and 241Am), and that of the main dose-producing radionuclides (129I, 137Cs and 90Sr) were determined. The uniformity of the Al, Ag, NO3, 129I, 137Cs and 90Sr distribution in the columns was estimated.

在Mayak生产协会积累的含碘吸附剂废进行了化学和放射化学分析。测量了吸附剂大组分(Al、Ag、NO3 -和总I)和相关杂质(F -、Cl -和SO42 -)的质量分数。测定了总α-和β-比活度、可分析鉴定的长寿命α-和β-发射核素(99Tc、U、Pu同位素和241Am)的比活度,以及主要产生剂量的核素(129I、137Cs和90Sr)的比活度。评价了Al、Ag、NO3 -、129I、137Cs和90Sr在塔中分布的均匀性。
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引用次数: 0
Mineral-Like Consolidating Matrix Materials for Solidification of Technetium and Technetium–Neptunium Fractions 用于凝固锝和锝-镎馏分的类矿物固结基质材料
IF 1 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-10-13 DOI: 10.1134/S1066362225040125
K. K. Korchenkin, V. A. Orlova, A. V. Gazdanova, N. V. Lavina

The phase formation of the phosphates Tc0.5Zr0.5P2O7, Tc0.25Zr0.75P2O7, and Tc0.25Np0.25Zr0.5P2O7 for the immobilization of technetium and technetium–neptunium fractions was studied. The powders were obtained by precipitation from solution. The target phase formation temperature was 600°C. The compounds obtained are single-phase products and crystallize in the cubic system, space group Pa–3. The solidification of the real technetium–zirconium fraction from VVER-1000 SNF processing was performed. The hydrolytic durability of the samples was studied by long-term static leaching. The degrees of leaching were as follows: Tc, no more than 0.03%; Np, 0.008%; Zr, less than 0.001%.

研究了磷酸盐Tc0.5Zr0.5P2O7、Tc0.25Zr0.75P2O7和Tc0.25Np0.25Zr0.5P2O7在固载锝和锝-镎馏分中的相形成。粉末由溶液沉淀法得到。目标相形成温度为600℃。所得化合物为单相产物,在立方体系中结晶,空间群为Pa-3。研究了VVER-1000 SNF工艺中实际工艺锆组分的凝固过程。通过长期静态浸出研究了样品的水解耐久性。浸出程度为:Tc,不大于0.03%;Np, 0.008%;Zr,小于0.001%。
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引用次数: 0
Reactor Production of 147Pm 反应堆生产147Pm
IF 1 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-10-13 DOI: 10.1134/S1066362225040095
K. V. Rotmanov, V. A. Tarasov, V. V. Lobanenko, G. V. Goncharova, A. A. Lykova, O. I. Andreev

147Pm is used in industry in sealed radioactive sources for measuring the thickness or density of materials and as a power source in radioisotope thermoelectric generators for space research. Traditionally, 147Pm is isolated from a mixture of fission fragments of heavy nuclei. An alternative method for producing the radionuclide is irradiation of neodymium with neutrons from a nuclear reactor. At the Research Institute of Atomic Reactors, reactor irradiation of neodymium oxide of natural isotopic composition was carried out and a pilot batch of 147Pm was obtained.

147Pm在工业中用于密封放射源,用于测量材料的厚度或密度,并作为空间研究的放射性同位素热电发电机的动力源。传统上,147Pm是从重核裂变碎片的混合物中分离出来的。另一种生产放射性核素的方法是用核反应堆中的中子照射钕。在原子反应堆研究所,进行了天然同位素组成氧化钕的反应堆辐照,获得了147Pm的中试批次。
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引用次数: 0
To 95th Birthday Anniversary of Academician Boris Fedorovich Myasoedov 为鲍里斯·费奥多罗维奇·米亚索耶多夫院士95周年诞辰而干杯
IF 1 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-10-13 DOI: 10.1134/S1066362225040198
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引用次数: 0
Addressing Nuclear Legacy Problems and the Role of Fundamental Radiochemistry 解决核遗留问题和基础放射化学的作用
IF 1 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-10-13 DOI: 10.1134/S1066362225040010
L. A. Bolshov, I. I. Linge, S. S. Utkin

The article discusses the key milestones in the establishment of the Unified State System for Radioactive Waste Management in the Russian Federation. It summarizes the main achievements from the implementation of two Federal Target Programs for Nuclear and Radiation Safety in Russia. The article evaluates the role that the Russian Academy of Sciences and its organizations play in addressing some fundamental problems associated with nuclear and radiation safety at nuclear legacy facilities, as well as with the management of spent nuclear fuel and accumulated radioactive waste.

本文讨论了在俄罗斯联邦建立统一的国家放射性废物管理系统的关键里程碑。报告总结了俄罗斯核与辐射安全两个联邦目标计划实施的主要成果。本文评估了俄罗斯科学院及其组织在处理与核遗留设施的核与辐射安全有关的一些基本问题,以及在管理乏燃料和积累的放射性废物方面所发挥的作用。
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引用次数: 0
Evaluation of Radon Exhalation from Vegetables with Estimation of the Lifetime Radiological Cancer Risk 蔬菜氡释放量的评价与终生放射致癌风险的估计
IF 1 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-10-13 DOI: 10.1134/S1066362225040174
K. K. M. Amin, N. F. Salih

The natural radioactivity levels in vegetable samples and the radon concentrations in 18 different types of vegetables collected from Bazyan location in Kurdistan Iraqi region were determined. CR-39 detector with a PVC tube was used to record the tracks density of alpha particles emitted by radon from vegetable samples. The results showed that the concentration of radon released from vegetable samples ranged from highest value of 311 Bq m–3 in sample A12 (green peppers) to lowest value 9.8 Bq.m–3 in sample A10 (wild rocket) with the average concentration of 162 Bq m–3. The concentrations of radon released from vegetable samples were lower than the global permissible limit of the exposure to radon according to International Commission on Radiological Protection (ICRP) and International Atomic Energy Agency (IAEA), 200–800 Bq m–3, and lower than the limit in foods, 400 Bq m–3, according to ICRP. Thus, the samples studied pose no health risks.

测定了伊拉克库尔德斯坦巴兹扬地区采集的蔬菜样品中的天然放射性水平和18种不同蔬菜中的氡浓度。采用PVC管CR-39型探测器,记录了蔬菜样品氡释放α粒子的径迹密度。结果表明:蔬菜样品的氡释放浓度在A12(青椒)样品中最高为311 Bq m-3,最低为9.8 Bq。样品A10(野火箭)中m-3的平均浓度为162 Bq m-3。根据国际放射防护委员会(ICRP)和国际原子能机构(IAEA)的规定,蔬菜样品释放的氡浓度低于氡暴露的全球允许限值200-800 Bq - m-3,低于食品中的限值400 Bq - m-3。因此,所研究的样本不构成健康风险。
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引用次数: 0
Preparation and Characterization of Nano Silicotitanate Gel to be Used as a Base Material for 99Mo/99mTc and 188W/188Re Chromatographic Column Radionuclide Generators 用作99Mo/99mTc和188W/188Re色谱柱放射性核素发生器基材的纳米钛酸硅凝胶的制备与表征
IF 1 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-10-13 DOI: 10.1134/S1066362225040113
M. A. Tawfic, M. Mostafa, H. E. Ramadan, M. A. El-Absy, W. H. Mahmoud

Nano silicotitanate (SiTi) gel was prepared to test its sorption capacity for Mo(VI) and W(VI) and its performance as a base material for 99Mo/99mTc and 188W/188Re chromatographic column generators. X-ray diffraction analysis showed that SiTi is a crystalline material with a crystallite size of 5.5 nm. High-resolution TEM studies showed that the average particle size was 60 nm. According to field emission SEM studies, SiTi has a cloudy morphology with the presence of many cavities. As indicated by TGA and EDX studies, SiTi gel has the chemical formula SiTi6O11·7H2O. Nitrogen chromatographic studies showed that SiTi has a BET surface area of 285 m2/g, total pore volume of 0.31 cm3/g, and average pore diameter of 3.7 nm. DLS studies showed that the hydrodynamic diameter distribution of SiTi particles is bimodal, with 86.5% of particles corresponding to the peak at 126.5 nm and 13.5%, to the peak at 724.4 nm. Electrophoresis studies indicated that SiTi gel has a zeta potential of –45.1 mV. According to Langmuir sorption isotherms, SiTi gel showed molybdate(VI)-99Mo and tungstate(VI)-188W maximum capacities in the ranges 162.87–192.31 and 67.93–196.85 mg/g, respectively, in the temperature range 25–60°C. The breakthrough capacities for 99Mo and 188W were found to be 69.8 mg Mo/g and 60 mg W/g, respectively. 99Mo/99mTc and 188W/188Re chromatographic column generators were prepared and successfully eluted to obtain 99mTc and 188Re with the average elution yields of 89.1 and 97.9%, respectively, and radiochemical purity of >97 % (as pertechnetate and perrhenate, respectively).

制备了纳米硅钛酸盐(SiTi)凝胶,测试了其对Mo(VI)和W(VI)的吸附能力,以及作为99Mo/99mTc和188W/188Re色谱柱发生器的基材性能。x射线衍射分析表明,硅钛为结晶材料,晶粒尺寸为5.5 nm。高分辨率透射电镜研究表明,平均粒径为60 nm。根据场发射扫描电镜研究,硅钛具有多云的形态,存在许多空腔。经TGA和EDX研究表明,SiTi凝胶的化学式为SiTi6O11·7H2O。氮色谱研究表明,SiTi的BET比表面积为285 m2/g,总孔体积为0.31 cm3/g,平均孔径为3.7 nm。DLS研究表明,SiTi颗粒的水动力直径分布为双峰型,86.5%的颗粒对应于126.5 nm处的峰值,13.5%的颗粒对应于724.4 nm处的峰值。电泳研究表明,SiTi凝胶具有-45.1 mV的zeta电位。根据Langmuir吸附等温线,在25 ~ 60℃的温度范围内,SiTi凝胶的最大容量分别为钼酸盐(VI)-99Mo和钨酸盐(VI)-188W,分别为162.87 ~ 192.31和67.93 ~ 196.85 mg/g。99Mo和188W的突破容量分别为69.8 mg Mo/g和60 mg W/g。制备了99Mo/99mTc和188W/188Re色谱柱发生器,成功洗脱得到99mTc和188Re,平均洗脱率分别为89.1%和97.9%,放射化学纯度为97%(分别为高技术酸盐和高透酸盐)。
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引用次数: 0
Reactions of Actinide Ions with 2,6-Pyridinedicarboxylic Acid in Aqueous Solutions and the Structure of Crystalline Compounds 锕系离子与2,6-吡啶二羧酸在水溶液中的反应及晶体结构
IF 1 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-10-13 DOI: 10.1134/S1066362225040046
B. F. Myasoedov, A. M. Fedoseev, V. P. Shilov

The results of studying the interaction of An(III–VI) with 2,6- pyridinedicarboxylic acid (2,6-PDCA) are summarized. The stability constants are estimated for complexes AnIV(PDC)n4–2n (n = 1–3). The total stability constant exceeds 1025 mol–3 L–3 and increases in the series from Th(IV) to Pu(IV) by 8 orders of magnitude. The difference in the stability of the An(III) and An(IV) complexes leads to rapid oxidation of Pu(III) to Pu(IV) with oxygen in the presence of 2,6-PDCA. An(V) and An(VI) ions form 1 : 1 and 1 : 2 complexes with PDC. The formation of An(IV,V,VI) complexes leads to a shift in the redox potential of the (V)/(IV) and (VI)/(V) couples. An(V) disproportionate in the presence of 2,6-PDCA anions. For An(VI) complexes of 1 : 2 composition, the ff transition bands are weakened, which is associated with the centrosymmetrical structure of the coordination polyhedron of the An atom. The stability of the An(VI) complexes was evaluated. An(III) ions form compounds with PDC2– in which the metal : ligand ratio is 1 : 3. Compounds AnIV(PDC)2 and those with an anionic moiety in the form of AnIV(PDC)32– were obtained. The cations were imidazole, Cs+, Ln2+, and Ln3+. An(V) forms compounds with one and two PDC2– ions. Compounds of UO22+ with PDC2–, as well as UO2(PDC)22– compounds with organic and inorganic outer-sphere cations have been studied. According to X-ray diffraction analysis, the AnO2(PDC)22– have the center of symmetry. In the isostructural series [Li2AnO2(PDC)2]·2H2O, actinide contraction is expressed in a decrease in the An=O distances in the “yl” groups from U to Pu. In all cases, PDC2– is coordinated in the tridentate fashion through two oxygen atoms of carboxyl groups and a nitrogen atom.

综述了An(III-VI)与2,6-吡啶二羧酸(2,6- pdca)相互作用的研究结果。估计了配合物AnIV(PDC) n4-2n (n = 1-3)的稳定性常数。总稳定常数超过1025 mol - 3l - 3,从Th(IV)到Pu(IV)依次增加8个数量级。An(III)和An(IV)配合物稳定性的差异导致在2,6- pdca存在下,Pu(III)在氧的作用下迅速氧化为Pu(IV)。安(V)和安(VI)离子与PDC形成1:1和1:1的配合物。An(IV,V,VI)配合物的形成导致(V)/(IV)和(VI)/(V)对氧化还原电位的变化。a (V)在2,6- pdca阴离子存在下不成比例。对于1:2组成的An(VI)配合物,f-f跃迁带减弱,这与An原子的配位多面体的中心对称结构有关。评价了An(VI)配合物的稳定性。An(III)离子与PDC2 -形成金属与配体比例为1:3的化合物。得到了化合物AnIV(PDC)2和以阴离子形式存在的化合物AnIV(PDC)32 -。阳离子为咪唑、Cs+、Ln2+和Ln3+。An(V)与一个和两个PDC2 -离子形成化合物。研究了UO22+与PDC2 -的化合物,以及UO2(PDC)22 -与有机和无机外球阳离子的化合物。根据x射线衍射分析,AnO2(PDC)22 -具有对称中心。在同构系列[Li2AnO2(PDC)2]·2H2O中,锕系元素的收缩表现为从U到Pu的“yl”基团An=O距离的减小。在所有情况下,PDC2 -通过两个羧基氧原子和一个氮原子以三叉戟方式配位。
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引用次数: 0
Extraction of Actinides and Lanthanides from Nitric Acid Media with Alkylated Phosphoryl Ketones 烷基化磷酰酮萃取硝酸介质中锕系元素和镧系元素的研究
IF 1 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-10-13 DOI: 10.1134/S1066362225040083
A. M. Safiulina, A. V. Lizunov, N. E. Borisova, A. V. Golubev, D. A. Tatarinov, V. F. Mironov, I. G. Tananaev

Extraction of actinides and lanthanides from nitric acid media with 4-(di-n-alkylphosphoryl)-4-methylpentan-2-one derivatives with different lengths of alkyl substituents at the phosphorus atom [hexyl (C6), octyl (C8), and decyl (C10)] was studied. High selectivity was demonstrated in the extractive separation of uranium(VI), thorium(IV), and rare earth elements (REEs) with the separation factor for U(VI) and the sum of REEs SFU(VI)/ΣREE > 4500 and for thorium(IV) and the sum of REEs SFTh(IV)/ΣREE > 5000. The influence of alkyl radicals at the phosphorus atom on the extraction capacity for f-elements was shown. The extraction capacity increases in the series C6 < C8 < C10. Isotherms of uranium(VI) and thorium(IV) extraction with γ-(dialkylphosphoryl) ketones C6, C8 and C10 were obtained.

研究了磷原子上具有不同长度烷基取代基的4-(二烷基磷基)-4-甲基戊烷-2- 1衍生物[己基(C6)、辛基(C8)和癸基(C10)]从硝酸介质中萃取锕系元素和镧系元素。铀(VI)、钍(IV)和稀土元素(ree)的分离因子分别为SFU(VI)/ΣREE >; 4500和钍(IV)、SFTh(IV)/ΣREE > 5000,对铀(VI)、钍(IV)和稀土元素(ree)具有较高的选择性。研究了磷原子上的烷基自由基对f元素萃取能力的影响。C6 < C8 <; C10系列萃取量增大。得到了γ-(二烷基磷酰)酮C6、C8和C10萃取铀(ⅵ)和钍(ⅳ)的等温线。
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引用次数: 0
Behavior of Beryllium-7 in Air in the Region of the Nuclear Industrial Complex in Sosnovyi Bor, Leningrad Oblast, Russia 俄罗斯列宁格勒州索斯诺维博尔核工业园区空气中铍-7的行为
IF 1 Q4 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-08-07 DOI: 10.1134/S1066362225030178
D. R. Itygina, E. B. Pankina, M. P. Glukhova, V. F. Kireev

The 7Be activity in near-surface atmospheric aerosols and in atmospheric precipitations that fell out on the territory of the Aleksandrov Research Institute of Technology during the eight-year period covering the end of the 24th and the beginning of the 25th solar activity cycles (2016–2023) are reported. The many-year mean volume activity of 7Be in atmospheric aerosols was calculated from the monthly data of the radiation monitoring of the atmosphere at four posts of the automated radiation monitoring system; the value of 3.2 mBq/m3 was obtained. The seasonal trends in variation of the 7Be volume activity in air with a gradual increase from January to a maximum in June, followed by a decrease in the second half of the year, were determined. The inverse dependence of the annual mean volume activity of 7Be in the aerosols on the solar activity (Wolf numbers) was confirmed. The correlation coefficients of the 7Be activity in aerosols with the weather parameters (air temperature, relative humidity, wind speed, atmospheric pressure, and amount of precipitations) were calculated. The independence of the 7Be content in atmospheric aerosols from anthropogenic factors and trends in the variation of its volume activity during a year cycle allow 7Be to be used in the future as a natural tracer for evaluating the air pollution with manmade radionuclides.

本文报道了从第24个太阳活动周期结束到第25个太阳活动周期开始(2016-2023)的8年期间,在亚历山德罗夫技术研究所(Aleksandrov Research Institute of Technology)领土上的近地表大气气溶胶和大气降水中的7Be活动。利用辐射自动监测系统4个站点逐月的大气辐射监测数据,计算了大气气溶胶中7Be的多年平均体积活度;结果为3.2 mBq/m3。大气中7Be体积活度的季节变化趋势为:从1月逐渐增加到6月达到最大值,然后在下半年下降。证实了气溶胶中7Be的年平均体积活度与太阳活动(Wolf数)呈负相关。计算了气溶胶中7Be活度与气温、相对湿度、风速、气压、降水量等气象参数的相关系数。大气气溶胶中的7Be含量不受人为因素的影响,其体积活度在一年周期内的变化趋势使7Be在未来可作为评价人造放射性核素空气污染的天然示踪剂。
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引用次数: 0
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Radiochemistry
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