Radiochemistry最新文献_第4页

Measurement of Radon and Thoron Concentrations in Rock Samples from the Iraqi Kurdistan Region Using Track Etch Detectors 利用径迹蚀刻探测器测量伊拉克库尔德斯坦地区岩石样品中的氡和钍浓度

IF 0.9

Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S1066362224060195

H. M. Qadr

引用次数: 0

Temperature Dependence of the Sorption and Distribution of Cs, Sr, and Am on Fractured Rock Minerals of the Nizhnekansky Massif 下日涅坎斯基地块裂隙岩矿物中Cs、Sr、Am吸附与分布的温度依赖性

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Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S1066362224060183

A. A. Rodionova, I. E. Vlasova, V. O. Yapaskurt, V. G. Petrov, S. E. Vinokurov

{"title":"Temperature Dependence of the Sorption and Distribution of Cs, Sr, and Am on Fractured Rock Minerals of the Nizhnekansky Massif","authors":"A. A. Rodionova, I. E. Vlasova, V. O. Yapaskurt, V. G. Petrov, S. E. Vinokurov","doi":"10.1134/S1066362224060183","DOIUrl":"10.1134/S1066362224060183","url":null,"abstract":"The heat generation by high-level waste raises the temperature in the near-surface zone of the repository, and the effect of this factor on the behavior of radionuclides in the host fractured rock environment upon deep disposal of radioactive waste (RW) should be considered in predictive modeling. The sorption behavior and spatial distribution of Cs, Sr, and Am on the surface of a fractured rock sample of the Nizhnekansky massif depending on temperature were studied. The distribution coefficients of Sr and Am on the sample surface increase with increasing temperature from 25 to 70°C, whereas the Cs distribution coefficient does not increase. This difference may be associated with different mechanisms of the sorption of these radionuclides. Cs, Sr, and Am are nonuniformly distributed on mineral phases of the fractured sample and are preferentially retained on Ca(Sr)-zeolite forming the mineral composition of the fractures. The coefficients of the phase distribution of radionuclides on separate mineral phases/associations were determined by quantitative analysis.","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 6","pages":"927 - 936"},"PeriodicalIF":0.9,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143431002","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

An Integrated Closed Loop Flowsheet for Production of Highly Enriched 63Ni and Deposition of 63Ni Coatings 高富集63Ni生产及镀层沉积集成闭环流程

IF 0.9

Radiochemistry Pub Date : 2025-02-17 DOI: 10.1134/S1066362224060018

V. A. Mazgunova, A. I. Kostylev, V. A. Babain, M. Yu. Alyapyshev

引用次数: 0

Decontamination of Sodium in the Primary Circuit of Fast Sodium-Cooled Reactors 快速钠冷堆一次回路中钠的净化

IF 0.9

Radiochemistry Pub Date : 2024-12-11 DOI: 10.1134/S1066362224050096

A. V. Rovneiko, O. L. Tashlykov, I. A. Filin, A. P. Khomyakov, S. E. Shcheklein, A. N. Sesekin

{"title":"Decontamination of Sodium in the Primary Circuit of Fast Sodium-Cooled Reactors","authors":"A. V. Rovneiko, O. L. Tashlykov, I. A. Filin, A. P. Khomyakov, S. E. Shcheklein, A. N. Sesekin","doi":"10.1134/S1066362224050096","DOIUrl":"10.1134/S1066362224050096","url":null,"abstract":"Invaluable experience of the designing, construction, and operation of sodium-cooled fast reactors, of prolongation of their lifetime, and of their decommissioning has been accumulated in Russia. The BN-600 reactor facility is being prepared for repeated prolongation of the lifetime up to the year 2040. The problem of preparing BN-600 for the decommissioning becomes topical, because this final step of the life cycle of the power unit is time-, material-, and labor-consuming and requires expensive measures for reducing dose loads, the more so as this reactor type is unique. To reduce these expenditures, it is necessary to choose the most effective technologies. Problems of sodium pretreatment to remove radioactive impurities and thus to minimize the staff dose loads when draining the BN-600 sodium coolant and decommissioning the reactor facility are being discussed today. The paper presents data on the radioactive contamination of hot and cold parts of sodium circuits and on the ways of sodium treatment to remove impurities. The processes of sodium decontamination from cesium with MAVR small adsorbers and cesium-accumulating traps are considered in detail for the BN-350 reactor facility as example. The paper objectives are to inform specialists on the experience on treatment of sodium from the primary circuit and to recommend the positively assessed technologies. The study is aimed at justifying the need for removing cesium isotopes from sodium as a preliminary step to reduce the staff dose loads prior to the decommissioning of fast sodium-cooled reactors.","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 5","pages":"656 - 662"},"PeriodicalIF":0.9,"publicationDate":"2024-12-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142798525","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

Studying the Performance of Aminotrimethylenephosphonic Acid for the Removal of Iron with Subsequent Recovery of Uranium from Sulfate Leach Liquor 氨基三甲基膦酸在硫酸盐浸出液中除铁后回收铀的性能研究

IF 0.9

Radiochemistry Pub Date : 2024-12-11 DOI: 10.1134/S1066362224050059

Walid M. Youssef, Entesar M. El Gammal, Sherien H. Ahmed, Mostafa I. Amin

{"title":"Studying the Performance of Aminotrimethylenephosphonic Acid for the Removal of Iron with Subsequent Recovery of Uranium from Sulfate Leach Liquor","authors":"Walid M. Youssef, Entesar M. El Gammal, Sherien H. Ahmed, Mostafa I. Amin","doi":"10.1134/S1066362224050059","DOIUrl":"10.1134/S1066362224050059","url":null,"abstract":"This study examined the effectiveness of using aminotrimethylenephosphonic acid (ATMP) as a chelating agent to remove iron from Abu Zeneima sulfate leach liquor (AZSLL) and recover uranium as a result. Key parameters including pH, ATMP to sample volume ratio, contact time, and temperature were systematically examined to find the ideal conditions for iron removal. The findings revealed a remarkable selectivity in iron removal by precipitation with 0.05 M aminotrimethylenephosphonic acid (ATMP) per 10 mL of the sample: 90% of iron was precipitated, which is equivalent to approximately 20.5 mg, without adversely impacting uranium content. The iron amputation provided a favorable opportunity for the subsequent recovery of uranium, employing trioctylamine (TOA) as the extracting agent. TOA dissolved in benzene demonstrated efficiency in uranium recovery. The effect of the type of stripping solution, organic/aqueous phase volume ratio, contact time, and temperature on the uranium stripping was examined. Under the optimized conditions, with a maximum stripping efficiency of 98%, the uranium concentration in the resulting solution reached 451.58 mg/L.","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 5","pages":"624 - 632"},"PeriodicalIF":0.9,"publicationDate":"2024-12-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142798484","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

Investigation of the Causes of Appearance of Step-Shaped Form of Sorption Isotherm 阶梯吸附等温线出现原因的探讨

IF 0.9

Radiochemistry Pub Date : 2024-12-11 DOI: 10.1134/S1066362224050011

A. V. Voronina

引用次数: 0

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

IF 0.9

Radiochemistry Pub Date : 2024-12-11 DOI: 10.1134/S1066362224050151

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

引用次数: 0

Determination of the Fractionation Coefficient of Cesium-137 in an Aqueous Aerosol under Laboratory Condiotions 实验室条件下含水气溶胶中铯-137分馏系数的测定

IF 0.9

Radiochemistry Pub Date : 2024-12-11 DOI: 10.1134/S106636222405014X

K. Yu. Mokrov

{"title":"Determination of the Fractionation Coefficient of Cesium-137 in an Aqueous Aerosol under Laboratory Condiotions","authors":"K. Yu. Mokrov","doi":"10.1134/S106636222405014X","DOIUrl":"10.1134/S106636222405014X","url":null,"abstract":"It is known that the concentration ratio of chemical elements in an aqueous aerosol (AA) can differ significantly from that of the same elements in the aqueous medium (AM) from which this AA was formed. Different accumulation (fractionation) of elements in AA occurs in the surface microlayer of water and is observed only for water-soluble microimpurities, whereas dissolved salts present in macroscopic concentrations undergo no accumulation. For radionuclides, the relative fractionation coefficient F(X/Cs) is defined as the degree of accumulation of the activity of radionuclide X in AA relative to another, reference radionuclide (137Cs). The values of F(X/Cs) were determined previously under natural conditions in the region of V-9 intermediate-level liquid radioactive waste storage reservoir (Lake Karachay) by analyzing the ratio of the volume activities of the radionuclides in water, RW(Cs/X), and in AA (in air), RA(Cs/X): F(X/Cs) = RA(Cs/X)/RW(Cs/X). Attempts to estimate the absolute fractionation coefficient of 137Cs, F(Cs), in AA relative to its content in AM failed. A procedure was suggested for determining the absolute fractionation coefficient of 137Cs, F(Cs), in AA relative to its content in AM under laboratory conditions. The procedure was tested with a model AM with the parameters close to those of V-9 reservoir (137Cs volume activity 0.17 MBq/L, dry residue ~10 g/L). The integral value of F(137Cs) for the model AM (for all the aqueous aerosol particles of size smaller than ~100 μm) varied from 4.4 to 6.5.","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"66 5","pages":"702 - 708"},"PeriodicalIF":0.9,"publicationDate":"2024-12-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142798500","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

Obtaining Nitric Acid Solutions of Uranyl at Deficiency of NO3– Anions 缺乏NO3 -阴离子条件下铀酰硝酸溶液的制备

IF 0.9

Radiochemistry Pub Date : 2024-12-11 DOI: 10.1134/S1066362224050035

V. L. Sofronov, V. A. Lavrentyev

引用次数: 0

Optimal Temperatures and Dose Rates in Radiation-Thermal Processing of Oil Bitumen Sands 沥青砂辐射热加工的最佳温度和剂量率

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Radiochemistry Pub Date : 2024-12-11 DOI: 10.1134/S1066362224050102

L. Yu. Jabbarova, I. I. Mustafaev

引用次数: 0