Reconstructing neutron spectra from limited measured counts is a challenging inverse problem. This paper presents a dual-domain feature-enhanced deep unfolding network (DDFEDUN), integrating the advantages of compressed sensing and deep learning. By constructing a collaborative architecture consisting of a wavelet-domain deep unfolding module (WDDUM), a convolution-domain deep unfolding module (CDDUM), and a dual-scale denoising module (DSDM), the proposed method fully leverages the structural prior information of neutron spectra across multiple transformation domains. This approach effectively enhances the model’s feature representation capability and noise robustness. Experimental results have demonstrated that DDFEDUN achieves high-precision and stable reconstruction across various typical neutron spectra.
{"title":"A neutron spectrum unfolding method based on the dual-domain feature-enhanced deep unfolding network","authors":"Yanfei Liu, Chenyang Wang, Hao Zheng, Qingshan Yin, Dongdong Yang, Qi Li, Ning Lv","doi":"10.1007/s10967-025-10482-8","DOIUrl":"10.1007/s10967-025-10482-8","url":null,"abstract":"<div><p>Reconstructing neutron spectra from limited measured counts is a challenging inverse problem. This paper presents a dual-domain feature-enhanced deep unfolding network (DDFEDUN), integrating the advantages of compressed sensing and deep learning. By constructing a collaborative architecture consisting of a wavelet-domain deep unfolding module (WDDUM), a convolution-domain deep unfolding module (CDDUM), and a dual-scale denoising module (DSDM), the proposed method fully leverages the structural prior information of neutron spectra across multiple transformation domains. This approach effectively enhances the model’s feature representation capability and noise robustness. Experimental results have demonstrated that DDFEDUN achieves high-precision and stable reconstruction across various typical neutron spectra.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"334 11","pages":"7957 - 7966"},"PeriodicalIF":1.6,"publicationDate":"2025-10-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145612793","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-10-24DOI: 10.1007/s10967-025-10452-0
A. Syssaletin, E. Batyrbekov, Y. Baklanova, V. Yermakov, R. Nauryzbayev, N. Marks, R. Kips, A. Tompson, L. Dallas, A. Stratz
Since 2021, the National Nuclear Center (NNC) of the Republic of Kazakhstan has been successfully developing a project dedicated to nuclear forensics. The relevance of this project is underscored by Kazakhstan’s leading position in the global uranium mining and export market. The country operates research reactors and is involved in the production of experimental nuclear fuel. The nuclear forensics project is being implemented in several key areas: the project will develop competencies in laboratory research of samples, interpretation of results, and develop a prototype concept for the National Nuclear Forensics Library. In implementing these challenges, the NNC experts draw on the experience of colleagues from world-leading scientific and research centers. Designing a prototype National Nuclear Forensics Library (NNFL) is a challenging project. The solution to this task is based on the IAEA’s approaches, recommendations, and the experience gained from the construction of similar systems in other countries.
{"title":"Advancing nuclear forensics competencies at the National Nuclear Center of the Republic of Kazakhstan and conceptual development of a National Nuclear Forensics Library","authors":"A. Syssaletin, E. Batyrbekov, Y. Baklanova, V. Yermakov, R. Nauryzbayev, N. Marks, R. Kips, A. Tompson, L. Dallas, A. Stratz","doi":"10.1007/s10967-025-10452-0","DOIUrl":"10.1007/s10967-025-10452-0","url":null,"abstract":"<div><p>Since 2021, the National Nuclear Center (NNC) of the Republic of Kazakhstan has been successfully developing a project dedicated to nuclear forensics. The relevance of this project is underscored by Kazakhstan’s leading position in the global uranium mining and export market. The country operates research reactors and is involved in the production of experimental nuclear fuel. The nuclear forensics project is being implemented in several key areas: the project will develop competencies in laboratory research of samples, interpretation of results, and develop a prototype concept for the National Nuclear Forensics Library. In implementing these challenges, the NNC experts draw on the experience of colleagues from world-leading scientific and research centers. Designing a prototype National Nuclear Forensics Library (NNFL) is a challenging project. The solution to this task is based on the IAEA’s approaches, recommendations, and the experience gained from the construction of similar systems in other countries.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"334 12","pages":"8977 - 8987"},"PeriodicalIF":1.6,"publicationDate":"2025-10-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146007051","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
In situ treatment of uranium-containing wastewater from uranium mining areas remains a significant challenge. Herein, microorganisms resistance to uranium (VI) were isolated. Subsequently, sand column experiments were carried out using local ore as a carrier to immobilize the isolated microorganisms. The results demonstrated that the ore can effectively support a high microbial loading and exhibited favorable biocompatibility. Compared with the ore alone, the immobilized microorganisms displayed a more rapid and stable capacity for uranium transformation and removal. While the maximum removal efficiency of the ore alone reached only 50%, while that of the immobilized microorganisms achieved up to 99%. Furthermore, the influence of various reaction parameters on uranium removal performance was systematically investigated. Under optimal conditions of pH 7, temperature of 25°C, initial uranium concentration of 20 mg/L, and inoculation ratio of 10%, the removal efficiency of the ore-immobilized microorganisms reached 99.4%, with a residual uranium concentration of 0.12 mg/L. The mechanisms revealed that in-situ cultivated microorganisms efficiently converted soluble uranium (VI) into insoluble forms and stable adsorbed uranium (VI) ions, thereby significantly enhancing the uranium immobilization capacity of the ore carrier. The immobilized microorganisms reduced soluble uranium (VI) to insoluble U(IV) precipitates via biological reduction and other resistance pathways, achieving a level of uranium removal that far exceeded the adsorption capacity of the ore alone. These findings provide a solid theoretical foundation and reliable technical support for the efficient, stable, and environmentally sustainable bioremediation of uranium-containing wastewater.
{"title":"In situ microbial remediation of uranium-contaminated wastewater in stabilized uranium mining areas","authors":"Jianming Li, Haotong Guo, Zhiwu Lei, Eming Hu, Boyuan Zheng, Jinming Hu, Qingliang Wang","doi":"10.1007/s10967-025-10460-0","DOIUrl":"10.1007/s10967-025-10460-0","url":null,"abstract":"<div><p>In situ treatment of uranium-containing wastewater from uranium mining areas remains a significant challenge. Herein, microorganisms resistance to uranium (VI) were isolated. Subsequently, sand column experiments were carried out using local ore as a carrier to immobilize the isolated microorganisms. The results demonstrated that the ore can effectively support a high microbial loading and exhibited favorable biocompatibility. Compared with the ore alone, the immobilized microorganisms displayed a more rapid and stable capacity for uranium transformation and removal. While the maximum removal efficiency of the ore alone reached only 50%, while that of the immobilized microorganisms achieved up to 99%. Furthermore, the influence of various reaction parameters on uranium removal performance was systematically investigated. Under optimal conditions of pH 7, temperature of 25°C, initial uranium concentration of 20 mg/L, and inoculation ratio of 10%, the removal efficiency of the ore-immobilized microorganisms reached 99.4%, with a residual uranium concentration of 0.12 mg/L. The mechanisms revealed that in-situ cultivated microorganisms efficiently converted soluble uranium (VI) into insoluble forms and stable adsorbed uranium (VI) ions, thereby significantly enhancing the uranium immobilization capacity of the ore carrier. The immobilized microorganisms reduced soluble uranium (VI) to insoluble U(IV) precipitates via biological reduction and other resistance pathways, achieving a level of uranium removal that far exceeded the adsorption capacity of the ore alone. These findings provide a solid theoretical foundation and reliable technical support for the efficient, stable, and environmentally sustainable bioremediation of uranium-containing wastewater.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"334 11","pages":"8159 - 8168"},"PeriodicalIF":1.6,"publicationDate":"2025-10-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145612789","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-10-24DOI: 10.1007/s10967-025-10470-y
Xuan Anh Dao Lam, Van Thang Nguyen, Huu Ngan Thy Truong, Thi Yen Hong Huynh, Cong Hao Le
The 210Po isotope was used as a tracer to study the transfer of polonium from nutrient solution and soil to lettuce (Lactuca Sativa) grown in hydroponic and soil systems, respectively. The nutrient solution-to-lettuce transfer factors (TFw) ranged from 1.23 to 5.41 L kgfresh weight−1, with a mean value of 3.01 L kg fresh weight−1. The soil-to-lettuce transfer factors (TFs) were from 0.32 to 0.65, with a mean value of 0.51. The mean activity concentrations of 210Po (ACPo) in lettuce grown in hydroponic and soil systems were 4.8 Bq kgfresh weight−1 and 12.6 Bq kgfresh weight−1, respectively. The hydroponic system significantly reduces the ACPo in lettuce with a significant value (p) of 0.05. The effective dose rate (De) was estimated for the normal intake rate of lettuce in Vietnam. The mean De values were 3.6 μSv y−1 and 9.2 μSv y−1 estimated for lettuce grown in hydroponic and soil systems, respectively. The dose assessment shows that the ACPo in all lettuce samples poses no risk to humans.
采用210Po同位素作为示踪剂,分别研究了营养液和土壤中钋在水培和土壤系统中向生菜(Lactuca Sativa)的转移。营养液对生菜的转移因子(TFw)范围为1.23 ~ 5.41 L kg鲜重−1,平均值为3.01 L kg鲜重−1。土壤对生菜的转化因子(TFs)为0.32 ~ 0.65,平均值为0.51。水培系统和土壤系统生菜中210 - po (ACPo)的平均活性浓度分别为4.8 Bq kg鲜重- 1和12.6 Bq kg鲜重- 1。水培系统显著降低生菜ACPo,显著值(p)为0.05。估计了越南莴苣正常摄取率的有效剂量率(De)。水培系统和土壤系统莴苣的平均De值分别为3.6 μSv y - 1和9.2 μSv y - 1。剂量评估显示,所有生菜样本中的ACPo对人体没有风险。
{"title":"Transfer characteristics of polonium from nutrient solution and soil to lettuce (Lactuca Sativa) grown in hydroponic and soil systems","authors":"Xuan Anh Dao Lam, Van Thang Nguyen, Huu Ngan Thy Truong, Thi Yen Hong Huynh, Cong Hao Le","doi":"10.1007/s10967-025-10470-y","DOIUrl":"10.1007/s10967-025-10470-y","url":null,"abstract":"<div><p>The <sup>210</sup>Po isotope was used as a tracer to study the transfer of polonium from nutrient solution and soil to lettuce (<i>Lactuca Sativa</i>) grown in hydroponic and soil systems, respectively. The nutrient solution-to-lettuce transfer factors (TF<sub>w</sub>) ranged from 1.23 to 5.41 L kg<sub>fresh weight</sub><sup>−1</sup>, with a mean value of 3.01 L kg <sub>fresh weight</sub><sup>−1</sup>. The soil-to-lettuce transfer factors (TF<sub>s</sub>) were from 0.32 to 0.65, with a mean value of 0.51. The mean activity concentrations of <sup>210</sup>Po (AC<sub>Po</sub>) in lettuce grown in hydroponic and soil systems were 4.8 Bq kg<sub>fresh weight</sub><sup>−1</sup> and 12.6 Bq kg<sub>fresh weight</sub><sup>−1</sup>, respectively. The hydroponic system significantly reduces the AC<sub>Po</sub> in lettuce with a significant value (<i>p</i>) of 0.05. The effective dose rate (D<sub>e</sub>) was estimated for the normal intake rate of lettuce in Vietnam. The mean D<sub>e</sub> values were 3.6 μSv y<sup>−1</sup> and 9.2 μSv y<sup>−1</sup> estimated for lettuce grown in hydroponic and soil systems, respectively. The dose assessment shows that the AC<sub>Po</sub> in all lettuce samples poses no risk to humans.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"334 11","pages":"8041 - 8050"},"PeriodicalIF":1.6,"publicationDate":"2025-10-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145612792","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-10-24DOI: 10.1007/s10967-025-10458-8
Steven R. Biegalski, Kevin Le
The nuclear industry is continuing to grow and adopt new technologies to manufacture components. One of the technologies under consideration is additive manufacturing (AM). AM could make production of components at lower cost and could lessen lead times significantly. However, AM could be prone to proliferation risks. AM machines give off signatures during the manufacturing process, and these signatures offer an alternative means of observing the component. Correlations between these signatures and the geometry being manufactured could be developed; enabling proliferators as they could take advantage of these correlations to steal AM manufacturing instructions relating to nuclear technology. This work pertains to preliminary work exploring the feasibility of tapping into AM side channels to predict geometries being manufactured on AM machines. The feasibility of utilizing vibration to draw geometric correlations will be assessed on an Ultimaker 2 + thermoplastic 3D printer.
{"title":"Evaluation of additive manufacturing side channels for nuclear nonproliferation applications","authors":"Steven R. Biegalski, Kevin Le","doi":"10.1007/s10967-025-10458-8","DOIUrl":"10.1007/s10967-025-10458-8","url":null,"abstract":"<div><p>The nuclear industry is continuing to grow and adopt new technologies to manufacture components. One of the technologies under consideration is additive manufacturing (AM). AM could make production of components at lower cost and could lessen lead times significantly. However, AM could be prone to proliferation risks. AM machines give off signatures during the manufacturing process, and these signatures offer an alternative means of observing the component. Correlations between these signatures and the geometry being manufactured could be developed; enabling proliferators as they could take advantage of these correlations to steal AM manufacturing instructions relating to nuclear technology. This work pertains to preliminary work exploring the feasibility of tapping into AM side channels to predict geometries being manufactured on AM machines. The feasibility of utilizing vibration to draw geometric correlations will be assessed on an Ultimaker 2 + thermoplastic 3D printer.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"334 12","pages":"8913 - 8920"},"PeriodicalIF":1.6,"publicationDate":"2025-10-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10967-025-10458-8.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146007248","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-10-24DOI: 10.1007/s10967-025-10475-7
Moldir Aumalikova, Danara Ibrayeva, Kuralay Ilbekova, Elvira Mussayeva, Aigerim Shokabayeva, Madina Kairullova, Riza Medetkhan, Moldir Aisauyt, Dinara Bizhanova
This study investigates uranium concentration in urine among workers in different stages of Kazakhstan’s uranium production cycle—mining, processing, and fuel fabrication. A total of 619 urine samples were analyzed using inductively coupled plasma mass spectrometry (ICP-MS). The highest uranium concentrations were found in workers from in-situ leaching mining facilities. Statistical analysis revealed significant variability and skewed distributions across groups, with a proportion of workers exceeding the reference value of 0.9 µgL−1. The findings highlight the need for ongoing biomonitoring and further assessment of occupational exposure, particularly among residents living near uranium production sites.
{"title":"Determination of uranium concentration in urine of Kazakhstan uranium workers","authors":"Moldir Aumalikova, Danara Ibrayeva, Kuralay Ilbekova, Elvira Mussayeva, Aigerim Shokabayeva, Madina Kairullova, Riza Medetkhan, Moldir Aisauyt, Dinara Bizhanova","doi":"10.1007/s10967-025-10475-7","DOIUrl":"10.1007/s10967-025-10475-7","url":null,"abstract":"<div><p>This study investigates uranium concentration in urine among workers in different stages of Kazakhstan’s uranium production cycle—mining, processing, and fuel fabrication. A total of 619 urine samples were analyzed using inductively coupled plasma mass spectrometry (ICP-MS). The highest uranium concentrations were found in workers from in-situ leaching mining facilities. Statistical analysis revealed significant variability and skewed distributions across groups, with a proportion of workers exceeding the reference value of 0.9 µgL<sup>−1</sup>. The findings highlight the need for ongoing biomonitoring and further assessment of occupational exposure, particularly among residents living near uranium production sites.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"334 11","pages":"7727 - 7733"},"PeriodicalIF":1.6,"publicationDate":"2025-10-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145612791","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-10-17DOI: 10.1007/s10967-025-10450-2
Seung Beom Yoo, Ga Eun Oh, Geon Woo Son, Dong Gyu Lee, Kwang Pyo Kim
In water treatment facilities, naturally occurring radionuclides of soil and rock may be accumulated in groundwater during the treatment of drinking water. The objective of this study is to assess internal radiation doses due to NORM inhalation by workers in water treatment facilities in Korea. We analyzed flow of groundwater in water treatment facilities. Airborne particle concentration and activity concentration were measured using a large-capacity, individual air sampler and HPGe detector. The annual internal radiation dose ranged from 9.52 × 10–7 to 3.42 × 10–5 mSv y−1, which was less than the annual dose limit of the general public of 1 mSv y−1.
在水处理设施中,在饮用水处理过程中,土壤和岩石中天然存在的放射性核素可能积聚在地下水中。本研究的目的是评估韩国水处理设施工人吸入NORM的内辐射剂量。分析了水处理设施中地下水的流动情况。采用大容量单个空气采样器和HPGe检测仪测量空气颗粒物浓度和活度浓度。年内辐射剂量范围为9.52 × 10-7 ~ 3.42 × 10-5 mSv y - 1,低于一般公众1 mSv y - 1的年剂量限值。
{"title":"Radiological safety assessment for workers in water treatment facility due to NORM inhalation","authors":"Seung Beom Yoo, Ga Eun Oh, Geon Woo Son, Dong Gyu Lee, Kwang Pyo Kim","doi":"10.1007/s10967-025-10450-2","DOIUrl":"10.1007/s10967-025-10450-2","url":null,"abstract":"<div><p>In water treatment facilities, naturally occurring radionuclides of soil and rock may be accumulated in groundwater during the treatment of drinking water. The objective of this study is to assess internal radiation doses due to NORM inhalation by workers in water treatment facilities in Korea. We analyzed flow of groundwater in water treatment facilities. Airborne particle concentration and activity concentration were measured using a large-capacity, individual air sampler and HPGe detector. The annual internal radiation dose ranged from 9.52 × 10<sup>–7</sup> to 3.42 × 10<sup>–5</sup> mSv y<sup>−1</sup>, which was less than the annual dose limit of the general public of 1 mSv y<sup>−1</sup>.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"334 11","pages":"7857 - 7865"},"PeriodicalIF":1.6,"publicationDate":"2025-10-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145612616","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-10-17DOI: 10.1007/s10967-025-10464-w
Akshibahunlang Marngar, Vikas Dubey
Quartz is a common and geologically complex mineral that is most commonly used in thermoluminescence (TL) applications for dating geological events and radiation dosimetry. This review provides an overview of the TL behavior of quartz derived from igneous, metamorphic, and sedimentary environments, emphasizing how the means of formation influences defect structures, trap parameters and TL sensitivity. It summarizes experimental work on glow curve behaviors, defect centers chemistry, thermal and irradiation histories, and provides comparative perspectives across quartz types. Sedimentary quartz has the highest TL sensitivity and well-bleached trap populations, and is potentially the best for radiometric dating of geological events and retrospective environmental dosimetry. Applications as luminescence dating of geological events and retrospective dosimetry surrounding radiation exposure, are discussed as representable examples. Future research directions include recent advances in trap engineering, TL instrumentation, and Ai-analysis of glow curves, providing opportunities for standardizing methods of analysis and standardizing the methodology of quartz for luminescence-based technologies.
{"title":"Thermoluminescence (TL) properties of quartz from different geological settings and their implications for geological dating and radiation dosimetry","authors":"Akshibahunlang Marngar, Vikas Dubey","doi":"10.1007/s10967-025-10464-w","DOIUrl":"10.1007/s10967-025-10464-w","url":null,"abstract":"<div><p>Quartz is a common and geologically complex mineral that is most commonly used in thermoluminescence (TL) applications for dating geological events and radiation dosimetry. This review provides an overview of the TL behavior of quartz derived from igneous, metamorphic, and sedimentary environments, emphasizing how the means of formation influences defect structures, trap parameters and TL sensitivity. It summarizes experimental work on glow curve behaviors, defect centers chemistry, thermal and irradiation histories, and provides comparative perspectives across quartz types. Sedimentary quartz has the highest TL sensitivity and well-bleached trap populations, and is potentially the best for radiometric dating of geological events and retrospective environmental dosimetry. Applications as luminescence dating of geological events and retrospective dosimetry surrounding radiation exposure, are discussed as representable examples. Future research directions include recent advances in trap engineering, TL instrumentation, and Ai-analysis of glow curves, providing opportunities for standardizing methods of analysis and standardizing the methodology of quartz for luminescence-based technologies.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"334 11","pages":"7599 - 7621"},"PeriodicalIF":1.6,"publicationDate":"2025-10-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145612614","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-10-17DOI: 10.1007/s10967-025-10448-w
Marta L. V. Patricio, Daniel M. Bonotto
Natural radium isotopes (226Ra, 224Ra, 223Ra, and 228Ra) in groundwater reflect aquifer geochemistry, especially in uranium- and thorium-rich formations. This study compares three methodologies (M1, M2, M3) for measuring them in waters. M1 used the detection efficiency based on gamma energies from 228Ac to generate an efficiency vs. energy calibration curve. M2 utilized U and Th standards, consisting of pitchblended and monazite sand, to obtain the calibration curves. M3 accounted for matrix effects using a calibration curve based on 226Ra standards solutions of varied activity concentration. The methods were applied to groundwater samples provided from different Brazilian aquifer systems.
{"title":"Calibration methods for radium isotopes determination in waters by gamma-ray spectrometry using an HPGe detector","authors":"Marta L. V. Patricio, Daniel M. Bonotto","doi":"10.1007/s10967-025-10448-w","DOIUrl":"10.1007/s10967-025-10448-w","url":null,"abstract":"<div><p>Natural radium isotopes (<sup>226</sup>Ra, <sup>224</sup>Ra, <sup>223</sup>Ra, and <sup>228</sup>Ra) in groundwater reflect aquifer geochemistry, especially in uranium- and thorium-rich formations. This study compares three methodologies (M1, M2, M3) for measuring them in waters. M1 used the detection efficiency based on gamma energies from <sup>228</sup>Ac to generate an efficiency <i>vs.</i> energy calibration curve. M2 utilized U and Th standards, consisting of pitchblended and monazite sand, to obtain the calibration curves. M3 accounted for matrix effects using a calibration curve based on <sup>226</sup>Ra standards solutions of varied activity concentration. The methods were applied to groundwater samples provided from different Brazilian aquifer systems.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"334 11","pages":"7839 - 7849"},"PeriodicalIF":1.6,"publicationDate":"2025-10-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145612613","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-10-17DOI: 10.1007/s10967-025-10443-1
Chenxi Hou, Jian Ding, Wei Gong, Lianshun Li, Chunsheng Shi, Gang Zhang, Chengxing Zhang, Tinggui Yang
The treatment of radioactive graphite waste, especially due to 14C emissions, poses significant challenges. This review summarizes incineration-based volume reduction technologies and evaluates carbon isotopic separation methods. Fluidized-bed incineration offers high efficiency but requires effective control of 14C release. Among separation techniques, chemical exchange using CO2 is identified as the most practical. A three-stage treatment strategy is proposed: incineration, off-gas purification, and 14C separation. This integrated approach enables waste minimization, emission control, and potential 14C reuse, offering a feasible and sustainable solution for managing radioactive graphite waste.
{"title":"Research progress of radioactive graphite waste treatment technologies","authors":"Chenxi Hou, Jian Ding, Wei Gong, Lianshun Li, Chunsheng Shi, Gang Zhang, Chengxing Zhang, Tinggui Yang","doi":"10.1007/s10967-025-10443-1","DOIUrl":"10.1007/s10967-025-10443-1","url":null,"abstract":"<div><p>The treatment of radioactive graphite waste, especially due to <sup>14</sup>C emissions, poses significant challenges. This review summarizes incineration-based volume reduction technologies and evaluates carbon isotopic separation methods. Fluidized-bed incineration offers high efficiency but requires effective control of <sup>14</sup>C release. Among separation techniques, chemical exchange using CO<sub>2</sub> is identified as the most practical. A three-stage treatment strategy is proposed: incineration, off-gas purification, and <sup>14</sup>C separation. This integrated approach enables waste minimization, emission control, and potential <sup>14</sup>C reuse, offering a feasible and sustainable solution for managing radioactive graphite waste.</p></div>","PeriodicalId":661,"journal":{"name":"Journal of Radioanalytical and Nuclear Chemistry","volume":"334 11","pages":"7623 - 7632"},"PeriodicalIF":1.6,"publicationDate":"2025-10-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145612615","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}