Applied Radiation and Isotopes最新文献

{"title":"In situ electrochemical synthesis of copper-zinc ferrocyanide for removal of cesium in simulated liquid radioactive wastes","authors":"Wei Cao,&nbsp;Lanfang Hua,&nbsp;Huiqi Fan,&nbsp;Jie Fang,&nbsp;Guangtuan Huang","doi":"10.1016/j.apradiso.2025.111854","DOIUrl":"10.1016/j.apradiso.2025.111854","url":null,"abstract":"<div><div>This study employed in situ electrochemical synthesis of copper-zinc ferrocyanide (CuZnFC) to effectively remove Cs⁺ from simulated liquid radioactive wastes (LRWs). Through single-factor experiments, the optimal reaction conditions were established as follows: an initial pH of 8.0, a molar ratio of [Fe(CN)₆]^4- to Cs⁺ of 10:1, a reaction temperature of 25 °C, a current density of 6 mA·cm⁻², and a stirring rate of 400 r·min⁻¹, achieving a Cs⁺ removal rate of 99.978 %. The precipitate analysis revealed its composition as CuZn[Fe(CN)₆]·6.18H₂O, which exhibited a cubic crystal structure and rapidly absorbed Cs⁺ from the simulated liquid radioactive wastes.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111854"},"PeriodicalIF":1.6,"publicationDate":"2025-04-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143865214","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Adsorption capacity and mechanism of uranium by Fusarium verticillioides HX-3 isolated from a uranium mining site","authors":"Qin Li ,&nbsp;Guangwen Feng ,&nbsp;Henglei Chen ,&nbsp;Changlong Cai ,&nbsp;Peihong Mao","doi":"10.1016/j.apradiso.2025.111857","DOIUrl":"10.1016/j.apradiso.2025.111857","url":null,"abstract":"<div><div>Microorganisms that survive in extreme environments may possess special survival abilities. In this study, the adsorption capacity and mechanism of <em>F. verticillioides</em> HX-3, a fungus isolated from uranium mine wastewater, for uranium were investigated. Single factor batch experiments such as adsorption time, biomass dosage, pH, temperature, initial uranium concentration and coexisting ion were used to study the uranium adsorption capacity of biomass. The adsorption mechanism was further explored using kinetic, isothermal, thermodynamic models, and microscopic characterization techniques. The results demonstrated that under optimal experimental conditions, the biomass reached an adsorption capacity of 10.47 mg/g at a uranium concentration of 15 mg/L, with an adsorption efficiencies of 93 %. The study also revealed that the biomass adsorption process involves inhomogeneous multilayer chemisorption and exhibits spontaneous endothermic behavior. SEM-EDS analysis revealed that U(IV) primarily adsorbs onto the biomass surface. FTIR analysis showed that the functions that played the main role in the adsorption process were amino, hydroxyl, carbonyl, and acylamino groups. In summary, <em>F. verticillioides</em> HX-3 holds great potential for treating uranium-containing wastewater and can serve as an environmentally friendly biosorbent.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111857"},"PeriodicalIF":1.6,"publicationDate":"2025-04-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143854805","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Sorption behavior of 137Cs and 60Co onto raw and cellulose-modified Greek bentonite","authors":"Dianellou Iro ,&nbsp;Noli Fotini ,&nbsp;Kantiranis Nikolaos","doi":"10.1016/j.apradiso.2025.111850","DOIUrl":"10.1016/j.apradiso.2025.111850","url":null,"abstract":"<div><div>Sorption properties of Greek bentonite from Kimolos in raw form and after cellulose-radiation modification were investigated for removal of cesium and cobalt from aqueous solutions. The sorption experiments were undertaken under different metal concentrations, without and with interfering ions, in single as well as in binary systems and the aqueous phase was analyzed through gamma ray-spectrometry using ¹³⁷Cs and ⁶⁰Co as tracers. Kinetic experiments revealed an ion exchange process. The structural and physicochemical changes after modification and metal sorption were examined through X-ray diffraction (XRD), Fourier transformed infrared spectroscopy (FTIR), scanning electron microscopy with energy dispersive X-ray spectroscopy (SEM-EDS), whereas the pH of point of zero charge (pH_pzc) and cation exchange capacity (CEC) were also determined. Sorption isotherms were reproduced through non-linear mathematical models, like the modified competitive Langmuir (MCL) and extended Freundlich (EF) models and their prediction accuracy was statistically tested through paired <em>t</em>-test at the 95 % confidence level. The results showed that both materials exhibited significant capacities (117 and 90 mg g⁻¹ the raw and modified bentonite for Cs, and 98 and 78 mg g⁻¹ for Co respectively). Both ions were found to have antagonistic behaviour in the binary system.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111850"},"PeriodicalIF":1.6,"publicationDate":"2025-04-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143865215","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Densitometric measurement of 18O content of 18O-enriched water in relation to the production of 18F-labelled radiopharmaceuticals","authors":"Paula Y. Steinberg ,&nbsp;Franco T. Bietti ,&nbsp;Naila Gomez ,&nbsp;Guillermo Casale ,&nbsp;Horacio R. Corti","doi":"10.1016/j.apradiso.2025.111848","DOIUrl":"10.1016/j.apradiso.2025.111848","url":null,"abstract":"<div><div>The densities of mixtures of ordinary water and ¹⁸O enriched water have been measured all over the range of compositions, at temperatures between 293.15 and 313.15 K, using a vibrating-tube densitometer. From the error analysis of the density data in the ¹⁸O enriched water region (atom % ¹⁸O &gt; 95) we concluded that densitometry measurements with an accuracy of ±0.00002 g cm⁻³, provide a simple, precise and low-cost method to determine the ¹⁸O enrichment degree of recycled heavy oxygen water used to generate radiopharmaceuticals, such as [¹⁸F]fluoro-2-deoxy-D-glucose for the Positron-Emission Tomography (PET) scanning.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111848"},"PeriodicalIF":1.6,"publicationDate":"2025-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143868462","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Assessment of the level of uranium in groundwater and the role of public water purifiers in mitigating the concentration- A study from the south-western part of Bengaluru, Karnataka, India","authors":"D.N. Deepika ,&nbsp;M.R. Ambika ,&nbsp;M.B. Karthik Kumar ,&nbsp;N. Karunakara ,&nbsp;Sanjeev Kimothi ,&nbsp;N. Nagaiah","doi":"10.1016/j.apradiso.2025.111849","DOIUrl":"10.1016/j.apradiso.2025.111849","url":null,"abstract":"<div><div>Groundwater samples were gathered from various sites adjacent to Manchanabele Reservoir and their uranium concentration was measured using a Light Emitting Diode (LED) fluorimeter. The results show that the uranium concentration varied widely from 0.2 to 358.1 ppb, with a Geometric Mean (GM) of 16.51 ppb. According to the Atomic Energy Regulatory Board (AERB) and World Health Organization (WHO) standard values, high uranium concentrations are found in 23 % and 34 % of samples, respectively. Water samples from public water purifiers which use reverse osmosis were also taken from the same locations in order to comprehend the potential decrease in uranium content. The uranium concentration in these samples varied from 0.2 to 18.1 ppb, with a GM of 0.32 ppb. Every water sample taken from the water purifiers reveals a concentration that is well within the safe limit of 30 ppb. Uranium levels are found to be comparatively very less in purified waters than those collected directly from the borewells. From the measured concentration of uranium, the radiological risk parameters estimated in terms of lifetime cancer risk is in the range of 0.001x10⁻³ to 1.14x10⁻³ with GM of 0.05x10⁻³. The chemical toxicity risk measured as lifetime annual daily dose is found to range from 0.007 to 13.34 μg/kg/day with GM of 0.61 μg/kg/day for groundwater samples and 0.0006x10⁻³ to 0.05x10⁻³ with GM of 0.001x10⁻³, 0.0074–0.67 μg/kg/day with GM of 0.012 μg/kg/day for purified water samples. Annual Effective Dose (AED) for the different age group was estimated and the values for Infants, children and Adults are found to vary between 0.4 and 734.99 μSv/y with a GM of 33.88 μSv/y, 0.141–251.84 μSv/y with a GM of 11.61μSv/y and 0.17–310.60μSv/y with a GM of 14.32 μSv/y for groundwater samples and 0.41–37.14 μSv/y with GM of 0.65 μSv/y, 0.14–12.72 μSv/y with GM of 0.22 μSv/y, 0.17–15.69 μSv/y with GM of 0.27 μSv/y respectively for purified water samples. The physicochemical parameters like pH and Total Dissolved Solids (TDS) were also measured and the dependence of uranium concentration on these parameters has also been studied.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111849"},"PeriodicalIF":1.6,"publicationDate":"2025-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143852226","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Potential risks of in-situ microbial remediation of uranium-contaminated groundwater: Uranium release and remigration","authors":"Wang Liu ,&nbsp;Junwen Lv ,&nbsp;Jinxi Peng ,&nbsp;Zeyu Li","doi":"10.1016/j.apradiso.2025.111847","DOIUrl":"10.1016/j.apradiso.2025.111847","url":null,"abstract":"<div><div>After in-situ microbial remediation of uranium-contaminated groundwater, the environmental problems caused by the remigration of uranium immobilized in the aquifer due to microbial decay require attention. In this study, uranium-containing <em>Leifsonia</em> sp. spoilage was produced by natural decay of uranium-adsorbed <em>Leifsonia</em> sp.<em>.</em> Batch experiments were used to investigate the influence on uranium release from the <em>Leifsonia</em> sp. spoilage under the conditions of different pH, action time, and concentrations of the metal ions K⁺, Ca²⁺, Na⁺, Mg²⁺, and Zn²⁺. The remigration of immobilized uranium was simulated by the <em>Leifsonia</em> sp. spoilage sand column experiment. The release rate of uranium initially decreased with increasing pH, increased with increasing contact time, and then remained unchanged with increasing time; the release rate of uranium peaked at 4.98 % at pH 3 and 120 h. Compared to the absence of metal ions, the release rate of uranium increased by &gt;10 % under the action of metal ions, in which Ca²⁺had the greatest effect, up to 18.4 %. Furthermore, U(IV) in the spoilage was oxidized to U(VI), resulting in uranium release, and uranium release was related to hydroxyl, carboxyl, amino, and amide groups in the spoilage. The release kinetics of uranium were consistent with those of the Elovich and double constant models, indicating that the release of uranium was a multifactorial integrated chemical desorption process. In addition, the remigrated uranium in groundwater had two components: some of the uranium was released from the spoilage and migrated independently as uranyl ions, and some was present in the spoilage and migrated with the spoilage, the amount of the former being much greater than that of the latter. This study provides a theoretical basis for the rational use of microbial in-situ remediation of uranium-contaminated groundwater by in-situ leaching of uranium.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111847"},"PeriodicalIF":1.6,"publicationDate":"2025-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143854817","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Study of the influence of moderator material on sensitivity of the epithermal neutron flux detector using the 71Ga(n,γ)72Ga reaction","authors":"E. Byambatseren ,&nbsp;T. Bykov ,&nbsp;D. Kasatov ,&nbsp;Ia Kolesnikov ,&nbsp;S. Savinov ,&nbsp;T. Shein ,&nbsp;S. Taskaev","doi":"10.1016/j.apradiso.2025.111844","DOIUrl":"10.1016/j.apradiso.2025.111844","url":null,"abstract":"<div><div>An intense epithermal neutron flux is necessary for boron neutron capture therapy (BNCT), a promising technique for the treatment of malignant tumors. The epithermal neutron flux is an essential characteristic of the BNCT neutron beam, and its measurement is directly related to the reliability of the treatment planning system. Such a tool could be a cylindrical activation detector using ⁷¹Ga (n,γ)⁷²Ga reaction. In the detector, the activation material is positioned in the geometrical center of a cylinder moderator covered with cadmium foil. Two different teams of researchers calculated the sensitivities of detectors of the same size, but with different moderators which differ by a factor of 1.6. In this work, the effect of the moderator material on the sensitivity of the detector was experimentally studied.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111844"},"PeriodicalIF":1.6,"publicationDate":"2025-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143842628","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Novel adaptation of the BeOSL whole-body dosimeter for the measurement of the ICRU 95 quantity Hp","authors":"Gabriela T.P. Melo ,&nbsp;Helen J. Khoury ,&nbsp;Viviane K. Asfora ,&nbsp;Gabriel H.R.B. França ,&nbsp;Vinicius S.M. de Barros","doi":"10.1016/j.apradiso.2025.111839","DOIUrl":"10.1016/j.apradiso.2025.111839","url":null,"abstract":"","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111839"},"PeriodicalIF":1.6,"publicationDate":"2025-04-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143842629","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Comparative efficacy of reactor vs. accelerator-based boron neutron capture therapy in U87MG glioblastoma models","authors":"Kai Nishimura ,&nbsp;Kazuki Miura ,&nbsp;Hiroki Tanaka ,&nbsp;Minoru Suzuki ,&nbsp;Hiroyuki Nakamura","doi":"10.1016/j.apradiso.2025.111833","DOIUrl":"10.1016/j.apradiso.2025.111833","url":null,"abstract":"<div><div>Boron neutron capture therapy (BNCT) has emerged as a promising treatment for cancer, utilizing the interaction between thermal neutrons and boron-10 to selectively target and destroy cancer cells. This study evaluates the efficacy of BNCT using 4-borono-L-phenylalanine (BPA) in two different systems: reactor-based BNCT at Kyoto University Reactor (KUR) and accelerator-based BNCT at the Aomori Prefectural Quantum Science Center (QSC). The QSC cyclotron accelerator (HM-20V; Sumitomo Heavy Industries, Japan) operates a lower neutron generation capacity compared to the cyclotron accelerators (HM-30; Sumitomo Heavy Industries, Japan) used in clinical settings at Kansai BNCT Clinical Center in Osaka Medical Pharmaceutical University and Southern Tohoku Hospital. Using U87MG glioblastoma-bearing mouse models, we compared the therapeutic outcomes of both systems. This result may be partially attributed to the higher gamma-ray dose delivered by the QSC accelerator compared to KUR, which may enhance cytotoxic effects and help compensate for the lower neutron dose. Additionally, possible differences in overall neutron spectra delivered by the two different sources (KUR and QSC) used in the work described here could also have contributed to the observed outcomes.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111833"},"PeriodicalIF":1.6,"publicationDate":"2025-04-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143842548","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Optimization of the LaBr3 detector model using differential evolution algorithms","authors":"Irina V. Prozorova ,&nbsp;Radmila R. Sabitova ,&nbsp;Sergey V. Bedenko ,&nbsp;Ruslan A. Irkimbekov ,&nbsp;Yuriy A. Popov ,&nbsp;Stanislav N. Svetachev ,&nbsp;Kuanysh K. Samarkhanov","doi":"10.1016/j.apradiso.2025.111841","DOIUrl":"10.1016/j.apradiso.2025.111841","url":null,"abstract":"<div><div>In gamma-ray spectrometry, computational detector model allows determining absolute detector efficiency for non-standard sources with varying chemical compositions in the absence of volumetric calibration standards. This study focuses on developing a computational model of a LaBr₃(Ce) 1.5\" × 1.5″ scintillation detector based on characterization data. The detector was characterized using ¹³⁷Cs and ¹⁵²Eu point calibration sources placed at various positions relative to the detector cap. Modeling was performed using the MCNP6 code based on the Monte Carlo method. The initial modeling results revealed deviations between the calculated and experimental detector responses, which required model optimization. Optimization of the detector parameters was carried out using differential evolution algorithms. To verify the optimized LaBr₃ model, studies were conducted with a volumetric KCl source. The deviations between the calculated and experimental results fell within the error limits.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"221 ","pages":"Article 111841"},"PeriodicalIF":1.6,"publicationDate":"2025-04-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143828740","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}