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Characterization of Primordial Radionuclides in Cement Building Materials from Iraqi Kurdistan: Activity Concentrations and Radiological Parameters 伊拉克库尔德斯坦水泥建筑材料中原始放射性核素的表征：活性浓度和放射参数
IF 1
Radiochemistry Pub Date : 2026-03-31 DOI: 10.1134/S106636222601008X
H. M. Qadr
{"title":"Characterization of Primordial Radionuclides in Cement Building Materials from Iraqi Kurdistan: Activity Concentrations and Radiological Parameters","authors":"H. M. Qadr","doi":"10.1134/S106636222601008X","DOIUrl":"10.1134/S106636222601008X","url":null,"abstract":"<p>Cement samples obtained from Iraqi Kurdistan were analyzed to determine the activity concentrations and evaluate the associated radiological risks, with the aim of establishing effective exposure reduction measures. A sodium iodide thallium-activated scintillation detector was utilized for quantitative radioactivity analysis. The average activity concentrations of <sup>226</sup>Ra, <sup>232</sup>Th, and <sup>40</sup>K were found to be 65.6 ± 17.4, 81.8 ± 16.3, and 333.7 ± 79.8 Bq/kg, respectively. These measurements exceed the internationally recognized reference values of 35 Bq/kg for <sup>226</sup>Ra and 30 Bq/kg for <sup>232</sup>Th, while remaining below the 400 Bq/kg benchmark established for <sup>40</sup>K by UNSCEAR. A comprehensive suite of radiological hazard parameters was determined from the measured activity data, encompassing radium equivalent activity, air absorbed dose rate, gamma activity index, internal hazard index, annual effective dose, and excess lifetime cancer risk. Each calculated metric was systematically compared against internationally prescribed safety standards and regulatory limits. Statistical evaluation was performed to examine the distribution characteristics of radionuclide concentrations and their corresponding hazard parameters, employing skewness and kurtosis assessments, Shapiro–Wilk normality testing, and Pearson correlation analysis to explore interdependences among variables. These results establish critical reference data for radiation protection planning and contribute to the development of evidence-based regulatory standards governing construction material safety within the Kurdistan Region of Iraq.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"68 1","pages":"80 - 89"},"PeriodicalIF":1.0,"publicationDate":"2026-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147571151","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
Sorption Interaction of U(VI) Ions with Hydroxyapatite Nanoparticles in Different Textural Organizations 不同结构组织羟基磷灰石纳米颗粒对U（VI）离子的吸附作用
IF 1
Radiochemistry Pub Date : 2026-02-08 DOI: 10.1134/S1066362225060189
A. V. Severin, V. S. Pomortseva, I. E. Vlasova
{"title":"Sorption Interaction of U(VI) Ions with Hydroxyapatite Nanoparticles in Different Textural Organizations","authors":"A. V. Severin,&nbsp;V. S. Pomortseva,&nbsp;I. E. Vlasova","doi":"10.1134/S1066362225060189","DOIUrl":"10.1134/S1066362225060189","url":null,"abstract":"<p>The interaction of U(VI) with natural and synthesized hydroxyapatite Ca<sub>5</sub>(PO<sub>4</sub>)<sub>3</sub>(OH) is of interest for the retention of uranium migrating in the environment from various sources of anthropogenic pollution. Another potential application of hydroxyapatite is its use as a carrier for radiopharmaceuticals. In this case, in addition to the parameters of the uranium sorption onto the sorbent surface, it is necessary to study the influence of the structural features of hydroxyapatite nanoparticles on the <sup>230</sup>U retention on the sorbent surface. This study deals with the kinetic parameters and mechanisms of uranium sorption onto three textural modifications of hydroxyapatite, with the nanopID morphology before and after sorption, and with the strength of uranium retention on hydroxyapatite. The patterns obtained are of interest from both medical and radioecological viewpoints.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"67 6","pages":"864 - 872"},"PeriodicalIF":1.0,"publicationDate":"2026-02-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147337816","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
Nanosized Needle Petroleum Coke as a Promising Sorbent for Recovering Radionuclides from Aqueous Solutions 纳米针状石油焦作为一种有前途的吸附剂用于从水溶液中回收放射性核素
IF 1
Radiochemistry Pub Date : 2026-02-08 DOI: 10.1134/S1066362225060104
A. G. Kazakov, T. Yu. Ekatova, S. E. Vinokurov, B. F. Myasoedov
{"title":"Nanosized Needle Petroleum Coke as a Promising Sorbent for Recovering Radionuclides from Aqueous Solutions","authors":"A. G. Kazakov,&nbsp;T. Yu. Ekatova,&nbsp;S. E. Vinokurov,&nbsp;B. F. Myasoedov","doi":"10.1134/S1066362225060104","DOIUrl":"10.1134/S1066362225060104","url":null,"abstract":"<p>The possibility of using activated needle petroleum coke (NPC), a carbon nanomaterial with the specific surface area of approximately 2500–3500 m<sup>2</sup>/g, as a sorbent for recovering radionuclides from aqueous solutions was examined. The physicochemical properties of NPC and the distribution coefficients (<i>K</i><sub>d</sub>) of actinides, fission products, and radium on NPC samples in nitric acid, neutral, and weakly alkaline solutions, including those with high salt content, were determined. High salt concentrations favor an increase in <i>K</i><sub>d</sub>, which is untypical of carbon nanomaterials. NPC shows promise for recovering and concentrating uranium, americium, and rare earth element isotopes from contaminated groundwater, river water, and seawater and from solutions of neutralized liquid radioactive waste.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"67 6","pages":"856 - 863"},"PeriodicalIF":1.0,"publicationDate":"2026-02-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147337724","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
Effect of Benzyltriethylammonium Di-2-ethylhexyl Sulfosuccinate on the Extraction of Lanthanides(III) from Nitric Acid Solutions with Bis(diphenylphosphorylmethylcarbonylamino)alkanes 二-2-乙基己基琥珀酸苄三乙基铵对双（二苯基磷酸基甲基羰基氨基）烷烃从硝酸溶液中萃取镧系元素（III）的影响
IF 1
Radiochemistry Pub Date : 2026-02-08 DOI: 10.1134/S1066362225060086
A. N. Turanov, V. K. Karandashev, O. I. Artyushin, E. V. Sharova
{"title":"Effect of Benzyltriethylammonium Di-2-ethylhexyl Sulfosuccinate on the Extraction of Lanthanides(III) from Nitric Acid Solutions with Bis(diphenylphosphorylmethylcarbonylamino)alkanes","authors":"A. N. Turanov,&nbsp;V. K. Karandashev,&nbsp;O. I. Artyushin,&nbsp;E. V. Sharova","doi":"10.1134/S1066362225060086","DOIUrl":"10.1134/S1066362225060086","url":null,"abstract":"<p>The efficiency of the lanthanide(III) extraction from nitric acid solutions with bis(diphenylphosphorylmethylcarbonylamino)alkane (bis-CMPO) solutions in organic solvents significantly increases in the presence of an ionic liquid, benzyltriethylammonium di-2-ethylhexyl sulfosuccinate ([N<sub>222Bn</sub>]SSu), in the organic phase. The lanthanide(III) distribution ratios in the extraction from 3 M HNO<sub>3</sub> solution with bis-CMPO solutions in dichloroethane increased by more than two orders of magnitude in the presence of [N<sub>222Bn</sub>]SSu. Lanthanide(III) ions are extracted with mixtures of bis-CMPO and the ionic liquid in organic solvents via the cation-exchange mechanism. The influence of the structure of bis-carbamoylmethylphosphine oxides, kind of organic diluent, and HNO<sub>3</sub> concentration in the aqueous phase on the efficiency of the metal ion extraction into the organic phase containing the ionic liquid is discussed.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"67 6","pages":"840 - 845"},"PeriodicalIF":1.0,"publicationDate":"2026-02-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147337723","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
Many-Years Dynamics and Seasonal Fluctuations of Dissolved Radiocesium in a Pond in the Vicinity of the Fukushima Daiichi NPP 福岛第一核电站附近一个池塘中溶解放射性铯的多年动态和季节波动
IF 1
Radiochemistry Pub Date : 2026-02-08 DOI: 10.1134/S1066362225060220
A. V. Konoplev, Y. Wakiyama, Y. Igarashi, V. N. Golosov, K. Nanba
{"title":"Many-Years Dynamics and Seasonal Fluctuations of Dissolved Radiocesium in a Pond in the Vicinity of the Fukushima Daiichi NPP","authors":"A. V. Konoplev,&nbsp;Y. Wakiyama,&nbsp;Y. Igarashi,&nbsp;V. N. Golosov,&nbsp;K. Nanba","doi":"10.1134/S1066362225060220","DOIUrl":"10.1134/S1066362225060220","url":null,"abstract":"<p>The results of long-term (2015–2025) monitoring of dissolved <sup>137</sup>Cs activity concentration in water of Inkyozaka pond located in close vicinity of the Fukushima Daiichi NPP are presented. Regular seasonal variations of dissolved <sup>137</sup>Cs in pond water were observed concurrently with seasonal fluctuations of water temperature, which confirms their relation to the temperature dependence of the radiocesium desorption from sediments to solution. The activation energy of radiocesium desorption, obtained from the observational data, is 18.8 kJ/mol, which is in agreement with similar laboratory and field investigations. An empirical exponential model and a semiempirical diffusion model of long-term dynamics of dissolved <sup>137</sup>Cs in water of Inkyozaka pond were suggested. The modeling results qualitatively describe the seasonal fluctuations of the dissolved <sup>137</sup>Cs concentrations in the pond water.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"67 6","pages":"947 - 953"},"PeriodicalIF":1.0,"publicationDate":"2026-02-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1134/S1066362225060220.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147337823","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
High-Temperature Treatment of Mixed Uranium–Plutonium Nitride Spent Nuclear Fuel 铀-钚混合氮化乏燃料的高温处理
IF 1
Radiochemistry Pub Date : 2026-02-08 DOI: 10.1134/S1066362225060165
V. N. Momotov, D. E. Tikhonova, A. O. Makarov, A. Yu. Volkov, M. V. Mazannikov, A. M. Potapov, Yu. P. Zaikov
{"title":"High-Temperature Treatment of Mixed Uranium–Plutonium Nitride Spent Nuclear Fuel","authors":"V. N. Momotov,&nbsp;D. E. Tikhonova,&nbsp;A. O. Makarov,&nbsp;A. Yu. Volkov,&nbsp;M. V. Mazannikov,&nbsp;A. M. Potapov,&nbsp;Yu. P. Zaikov","doi":"10.1134/S1066362225060165","DOIUrl":"10.1134/S1066362225060165","url":null,"abstract":"<p>The efficiency of the high-temperature treatment (HTT) of mixed uranium–plutonium nitride spent nuclear fuel (MUPN SNF) to separate the fuel compound from the cladding and remove volatile fission products from the fuel was evaluated. The high-temperature treatment of SNF allows separation of the fuel compound from the cladding. The degree of removal of cesium nuclides from the fuel compound does not exceed 7%, whereas tritium, radiocarbon, and ruthenium are removed from the fuel compound to 94.2, 89.9, and 95.5%, respectively, relative to their initial content in SNF.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"67 6","pages":"899 - 908"},"PeriodicalIF":1.0,"publicationDate":"2026-02-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147337827","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
Decontamination of Aramid Personal Protective Equipment from Alpha and Beta Emitters 芳纶个人防护装备从α和β辐射源的净化
IF 1
Radiochemistry Pub Date : 2026-02-08 DOI: 10.1134/S1066362225060219
N. A. Kuznetsova, I. A. Orlova, M. V. Logunov
{"title":"Decontamination of Aramid Personal Protective Equipment from Alpha and Beta Emitters","authors":"N. A. Kuznetsova,&nbsp;I. A. Orlova,&nbsp;M. V. Logunov","doi":"10.1134/S1066362225060219","DOIUrl":"10.1134/S1066362225060219","url":null,"abstract":"<p>Procedures for decontamination of aramid-based personal protective equipment from combined alpha and beta contamination were developed at the Mayak Production Association. Only decontamination formulations containing reductants capable of reducing plutonium to the lower oxidation state (III) appeared to be effective. It was demonstrated that after five decontamination cycles based on the developed procedures, physicomechanical and protective properties of the aramid fabrics remained unchanged.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"67 6","pages":"939 - 946"},"PeriodicalIF":1.0,"publicationDate":"2026-02-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147337345","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
Modeling of Changes in the Composition of Uranium–Zirconium Carbonitride with an Oxygen Impurity Depending on Temperature and Burnup 含氧杂质的碳氮化铀锆组分随温度和燃耗变化的模拟
IF 1
Radiochemistry Pub Date : 2026-02-08 DOI: 10.1134/S1066362225060074
G. S. Bulatov, K. E. German
{"title":"Modeling of Changes in the Composition of Uranium–Zirconium Carbonitride with an Oxygen Impurity Depending on Temperature and Burnup","authors":"G. S. Bulatov,&nbsp;K. E. German","doi":"10.1134/S1066362225060074","DOIUrl":"10.1134/S1066362225060074","url":null,"abstract":"<p>Thermodynamic modeling of changes in the chemical and phase composition of uranium–zirconium carbonitride nuclear fuel U<sub>0.9</sub>Zr<sub>0.1</sub>(C<sub>0.495</sub>N<sub>0.495</sub>O<sub>0.01</sub>)<sub>0.995</sub> containing an oxygen impurity depending on the temperature (1600–2000 K) and burnup (1–10%) was performed. Under these conditions, accumulation of fission products in the fuel leads to the formation of a heterogeneous system consisting of a solid solution based on uranium–zirconium oxycarbonitride containing lanthanides and of separate condensed carbide, intermetallic, and oxide phases, of cesium and its iodide, of barium and its telluride, of strontium, and of technetium. The concentrations of these phases at the indicated temperatures and burnup levels were calculated.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"67 6","pages":"833 - 839"},"PeriodicalIF":1.0,"publicationDate":"2026-02-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147337718","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
Molten-Salt Reactor and Its Specific Features. Capture of Tritium and Radioactive Noble Gases in the Off-Gas Treatment System 熔盐反应器及其特点。废气处理系统中氚和放射性惰性气体的捕获
IF 1
Radiochemistry Pub Date : 2026-02-08 DOI: 10.1134/S1066362225060013
O. A. Kucherov, N. S. Pitelin, A. A. Semenov, A. S. Anikin, A. V. Anan’ev, A. M. Safiulina, A. V. Lizunov, I. G. Tananaev
{"title":"Molten-Salt Reactor and Its Specific Features. Capture of Tritium and Radioactive Noble Gases in the Off-Gas Treatment System","authors":"O. A. Kucherov,&nbsp;N. S. Pitelin,&nbsp;A. A. Semenov,&nbsp;A. S. Anikin,&nbsp;A. V. Anan’ev,&nbsp;A. M. Safiulina,&nbsp;A. V. Lizunov,&nbsp;I. G. Tananaev","doi":"10.1134/S1066362225060013","DOIUrl":"10.1134/S1066362225060013","url":null,"abstract":"<p>The paper deals with the specific features of the operation of molten-salt reactors (MSRs) as applied to the off-gas treatment systems for the localization of the main radiotoxic nuclides of iodine, tritium, and radioactive noble gases (RNGs). The domestic off-gas treatment system of a research MSR (RMSR), adopted by the Rosatom State Corporation, is compared to that of the Oak Ridge National Laboratory (ORNL, the United States, MSRЕ project). It is shown that the domestic research and development involved in the RMSR gas treatment strategy surpasses the world’s level owing to quantitative localization of molecular tritium from the gas phase, followed by its localization. This ensures radioecological safety of the reactor facility operation. The production rate of hazardous gaseous radionuclides (tritium, radioactive noble gas isotopes) in RMSR is calculated.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"67 6","pages":"771 - 784"},"PeriodicalIF":1.0,"publicationDate":"2026-02-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147337721","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
Development of a Process for Dynamic Sorption of Cesium from High-Level Waste onto a Regenerable Ferrocyanide Sorbent Using a Crossflow Membrane Micro-/Ultrafiltration Installation 横流膜微/超滤装置动态吸附高放废物中铯的工艺研究
IF 1
Radiochemistry Pub Date : 2026-02-08 DOI: 10.1134/S1066362225060141
M. V. Logunov, A. M. Zubov, Yu. A. Voroshilov
{"title":"Development of a Process for Dynamic Sorption of Cesium from High-Level Waste onto a Regenerable Ferrocyanide Sorbent Using a Crossflow Membrane Micro-/Ultrafiltration Installation","authors":"M. V. Logunov,&nbsp;A. M. Zubov,&nbsp;Yu. A. Voroshilov","doi":"10.1134/S1066362225060141","DOIUrl":"10.1134/S1066362225060141","url":null,"abstract":"<p>The possibility of the <sup>137</sup>Cs recovery by sorption onto ferrocyanide sorbents using a crossflow membrane filtration installation was examined. The steps of the sorption, washing, desorption, and sorbent regeneration were developed. This approach allows using the unsupported sorption material (nongranulated sorbent). Under comparable conditions, the sorption onto the nongranulated sorbent using a crossflow filtration installation occurs more efficiently than in the classical process of the column sorption onto the granulated sorbent. Namely, the process kinetics is better, the capacity is higher, and the effective filtration cycle is potentially higher. The contamination of the target cesium concentrate with products of the sorption material degradation is excluded.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"67 6","pages":"881 - 891"},"PeriodicalIF":1.0,"publicationDate":"2026-02-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147337346","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
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