Radiochemistry最新文献

Physicochemical Properties of Submicron 239Pu Aerosols 亚微米级 239Pu 气溶胶的物理化学特性

IF 0.9

Radiochemistry Pub Date : 2024-10-06 DOI: 10.1134/S1066362224040040

S. A. Sypko, V. E. Vvedensky, G. N. Bobov

引用次数: 0

Crystal and Molecular Structure of Binuclear Technetium Carbonyl Chloride Complexes [99TcCl(CO)3(C5H8O2)]2 (C5H8O2 = Acetylacetone) and [99TcCl(CO)4]2 双核氯化锝羰基配合物 [99TcCl(CO)3(C5H8O2)]2（C5H8O2 = 乙酰丙酮）和 [99TcCl(CO)4]2 的晶体和分子结构

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Radiochemistry Pub Date : 2024-10-06 DOI: 10.1134/S1066362224040027

G. V. Sidorenko, A. E. Miroslavov, V. V. Gurzhiy, A. R. Kochergina, A. P. Sakhonenkova, M. Yu. Tyupina, L. S. Chistyi, E. A. Pechertseva

{"title":"Crystal and Molecular Structure of Binuclear Technetium Carbonyl Chloride Complexes [99TcCl(CO)3(C5H8O2)]2 (C5H8O2 = Acetylacetone) and [99TcCl(CO)4]2","authors":"G. V. Sidorenko, A. E. Miroslavov, V. V. Gurzhiy, A. R. Kochergina, A. P. Sakhonenkova, M. Yu. Tyupina, L. S. Chistyi, E. A. Pechertseva","doi":"10.1134/S1066362224040027","DOIUrl":"10.1134/S1066362224040027","url":null,"abstract":"The crystal and molecular structures of the complex [99TcCl(CO)3(C5H8O2)]2 (C5H8O2 = Hacac = acetylacetone) formed in the course of prolonged standing of a [99Tc(acac)(CO)4] solution in ССl4/CDCl3 and of its analog containing no organic ligand, [99TcCl(CO)4]2, were determined. Both complexes contain a [Tc2(μ-Cl)2] four-membered ring. The remaining sites in the coordination sphere of the Tc atom are occupied by carbonyl ligands, and in the case of [99TcCl(CO)3(Hacac)]2, also by the neutral acetylacetone molecule in the enol form. The Hacac molecules in the binuclear complex are in the cis position to the Cl atoms in the octahedral surrounding of the Тс atoms and in the trans position to each other relative to the [Tc2(μ-Cl)2] ring. A comparative analysis of the geometries of the complexes and their known analogs was performed.","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 4","pages":"405 - 415"},"PeriodicalIF":0.9,"publicationDate":"2024-10-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142410323","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}

引用次数: 0

Thermal Stability of Dibenzo-21-crown-7 and Its Solution in 1,2-Dichloroethane in Contact with Nitrogen Dioxide 二苯并-21-冠醚-7 及其在 1,2-二氯乙烷中的溶液与二氧化氮接触时的热稳定性

IF 0.9

Radiochemistry Pub Date : 2024-10-06 DOI: 10.1134/S1066362224040076

A. M. Koscheeva, K. V. Shelamov, A. V. Rodin, A. V. Ananiev

引用次数: 0

Influence of Iron(III) Hydroxo Forms and Boric Acid on the State of Ruthenium-106 in Aqueous Solutions 铁（III）羟基形式和硼酸对水溶液中钌-106 状态的影响

IF 0.9

Radiochemistry Pub Date : 2024-10-06 DOI: 10.1134/S1066362224040039

V. Karankova, A. Radkevich, V. Torapava, A. Dashouk

引用次数: 0

Method of Coupled Processes in Studying Diffusion of Radioactive Waste Elements in the Pore Solution of Clay Materials 研究放射性废物元素在粘土材料孔隙溶液中扩散的耦合过程方法

IF 0.9

Radiochemistry Pub Date : 2024-10-06 DOI: 10.1134/S1066362224040179

K. V. Martynov, E. V. Zakharova

{"title":"Method of Coupled Processes in Studying Diffusion of Radioactive Waste Elements in the Pore Solution of Clay Materials","authors":"K. V. Martynov, E. V. Zakharova","doi":"10.1134/S1066362224040179","DOIUrl":"10.1134/S1066362224040179","url":null,"abstract":"A method of coupled processes was proposed to maintain concentrations in the model leachate of the radioactive waste phosphate matrix, which served as a source of elements in the study of through-diffusion of P, Se, Br, Mo, Cs, and U in the pore solution of compacted clay materials. The method consisted in adding an leachatable solid phase to the solution in the source chamber of the diffusion cell. The use of this method made it possible to stabilize the boundary conditions and expand the range of element concentrations in the source chamber of diffusion cells. The new as-obtained data on the effective diffusion coefficients of radioactive waste elements in clay rocks were used to refine the empirical models of diffusion transfer. It is shown that in different geochemical systems (model groundwater and phosphate glass leachate) for some elements (Br, Mo, Cs) it is possible to use unified models in the form of effective diffusion coefficients as a function of factors influencing this process: sample porosity, smectite content in the sample, and concentration of radionuclide (element) in pore solution, while for Se and U, diffusion models for various geochemical systems differ. The specificity of diffusion behavior of elements is associated with structural features and physicochemical properties of particles of these elements in aqueous solutions.","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 4","pages":"557 - 569"},"PeriodicalIF":0.9,"publicationDate":"2024-10-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142410322","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}

引用次数: 0

Localization of Iodine and Uranyl Carbonate Complex on Metal-Containing Clay Materials from Aqueous Media 碘和碳酸铀络合物在水介质含金属粘土材料上的定位

IF 0.9

Radiochemistry Pub Date : 2024-10-06 DOI: 10.1134/S1066362224040088

E. P. Krasavina, K. V. Martynov, K. G. Arzumanova, A. V. Gordeev, A. Yu. Bomchuk, V. O. Zharkova, S. A. Kulyukhin

引用次数: 0

Manganese(III,IV) Oxide-Based MDM Sorbent: Production, Sorption Characteristics, and Application for Purification of Liquid Radioactive Waste from Strontium and Radium Radionuclides 基于氧化锰（III,IV）的 MDM 吸附剂：锶和镭放射性核素的生产、吸附特性以及在液体放射性废物净化中的应用

IF 0.9

Radiochemistry Pub Date : 2024-10-06 DOI: 10.1134/S106636222404009X

V. V. Milyutin, O. A. Kononenko, N. A. Nekrasova

{"title":"Manganese(III,IV) Oxide-Based MDM Sorbent: Production, Sorption Characteristics, and Application for Purification of Liquid Radioactive Waste from Strontium and Radium Radionuclides","authors":"V. V. Milyutin, O. A. Kononenko, N. A. Nekrasova","doi":"10.1134/S106636222404009X","DOIUrl":"10.1134/S106636222404009X","url":null,"abstract":"The optimal conditions for the synthesis of a pelletized sorbent based on mixed Mn(III, IV) oxide by reacting aqueous solutions of MnSO4 and KMnO4 in an alkaline medium were determined: Mn2+/MnO4– molar ratio 1.70–1.80; pH of the reaction mixture 11.0–12.5; calcination temperature 220°C. For the sorbent fabricated under optimal conditions, the values of the distribution coefficient (Kd) of 90Sr in 0.01 M CaCl2 solution, static exchange capacity for calcium, hydromechanical strength of granules, and Kd of 90Sr as a function of the concentration of sodium and calcium ions were established. The sorbent afforded higher sorption characteristics with respect to strontium compared to known sorbents. A technology for producing pilot batches of the sorbent named MDM, was developed. Examples of the use of the MDM sorbent for the purification of various types of liquid radioactive waste from strontium and radium radionuclides are reported.","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 4","pages":"473 - 480"},"PeriodicalIF":0.9,"publicationDate":"2024-10-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142410298","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}

引用次数: 0

Contribution of RT-1 Radiochemical Plant to the Tritium Contamination in the Vicinity of Mayak Production Association RT-1 辐射化学厂对马雅克生产协会附近氚污染的影响

IF 0.9

Radiochemistry Pub Date : 2024-10-06 DOI: 10.1134/S1066362224040192

Yu. G. Mokrov

{"title":"Contribution of RT-1 Radiochemical Plant to the Tritium Contamination in the Vicinity of Mayak Production Association","authors":"Yu. G. Mokrov","doi":"10.1134/S1066362224040192","DOIUrl":"10.1134/S1066362224040192","url":null,"abstract":"Archive data (1970–2024) on the results of monitoring the tritium content of surface liquid radioactive waste (LRW) storage reservoirs (special radioactive waste repositories) and of groundwater in the vicinity of the Mayak Production Association are analyzed. The tritium contamination existing today was formed before the 1970s and was initially accumulated (a) in V-2 reservoir (Kyzyl-Tash), which operated as a reservoir for recirculating direct-cooling of industrial uranium–graphite reactors (PUGRs) in case of failure of uranium slug cladding; (b) in V-9 (Karachay) and V-17 (Staroye Boloto) reservoirs, which were used for storage of intermediate-level tritium-containing liquid waste; (c) in groundwater as a result of tritium seepage from the reservoirs. After putting into operation the RT-1 radiochemical plant (1977), the major fraction of tritium was accumulated in a new LRW type, tritium condensate, which was stored in V-17 reservoir. The contaminated groundwater filtering from V-17 reservoir was discharged only into an inlet of V-10 reservoir of the Techa Cascade of Reservoirs (TCR). The maximal rate of tritium discharge was estimated at 0.11 TBq/year, and the specific activity of tritium in the TCR water, at 2 Bq/L. In the 2020s, the tritium discharge into the atmosphere from the RT-1 plant was ~34 TBq, which was ~2800 times lower than the maximum permissible discharge prescribed for the whole enterprise. The mean value of the annual effective dose from all the pathways of tritium intake by Ozyorsk inhabitants was 0.26 μSv, and the maximal value was 0.49 μSv, which is ~2000 times lower than the dose limit of 1 mSv for the population. The tritium emissions and discharges from the RT-1 plant are negligible and exert virtually no radiation impact on the population.","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 4","pages":"576 - 588"},"PeriodicalIF":0.9,"publicationDate":"2024-10-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142410301","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}

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Uranium Sorption by Poly(hexamethylenesuccinamide) (PA46) as Cation-Exchange Resin from Wet-Process Egyptian Phosphoric Acid 埃及磷酸湿法工艺中作为阳离子交换树脂的聚亚甲基琥珀酰胺（PA46）对铀的吸附作用

IF 0.9

Radiochemistry Pub Date : 2024-10-06 DOI: 10.1134/S1066362224040106

W. M. Youssef, A. A. Elzoghby, A. A. Rateb, E. M. Helmy, K. A. Khalil, H. S. Gado

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Automated Synthesis of [N-Methyl-11C]choline, Radiopharmaceutical for Tumor Imaging by PET 用于 PET 肿瘤成像的放射性药物[N-甲基-11C]胆碱的自动合成

IF 0.9

Radiochemistry Pub Date : 2024-10-06 DOI: 10.1134/S106636222404012X

D. D. Vaulina, O. F. Kuznetsova, V. V. Orlovskaya, O. S. Fedorova, R. N. Krasikova

引用次数: 0