The limited global supply of actinium-225 remains a major bottleneck for its widespread clinical application in targeted alpha therapy, highlighting the importance of exploring alternative methods for large-scale production. In this study, the FLUKA and PHITS Monte Carlo transport code was employed to simulate the irradiation of thorium targets with protons, neutrons, and deuterons in the energy range of 20 to 800 MeV per nucleon. The production cross sections of 225Ac for different incident particles were systematically compared to identify the most promising production pathway for accelerator-based synthesis. Additionally, the study reports production cross section data for actinium, thorium, radium, and protactinium isotopes. By comparing the simulated results with available experimental data, the reliability of the nuclear reaction models was assessed, and directions for further refinement of Monte Carlo-based physical models in radionuclide production simulations were proposed.
{"title":"A study of 225Ac production cross section by proton, deuteron, and neutron irradiation on 232Th targets based on FLUKA and PHITS toolkit","authors":"Ke-Ying Zhu , Kai-Jin Yan , Gao-Long Zhang , Wei Zhang , Chang Cheng , Xiao-Yu Xu , Zhen Huang , Wei-Wei Qu","doi":"10.1016/j.apradiso.2026.112487","DOIUrl":"10.1016/j.apradiso.2026.112487","url":null,"abstract":"<div><div>The limited global supply of actinium-225 remains a major bottleneck for its widespread clinical application in targeted alpha therapy, highlighting the importance of exploring alternative methods for large-scale production. In this study, the FLUKA and PHITS Monte Carlo transport code was employed to simulate the irradiation of thorium targets with protons, neutrons, and deuterons in the energy range of 20 to 800 MeV per nucleon. The production cross sections of <sup>225</sup>Ac for different incident particles were systematically compared to identify the most promising production pathway for accelerator-based synthesis. Additionally, the study reports production cross section data for actinium, thorium, radium, and protactinium isotopes. By comparing the simulated results with available experimental data, the reliability of the nuclear reaction models was assessed, and directions for further refinement of Monte Carlo-based physical models in radionuclide production simulations were proposed.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"230 ","pages":"Article 112487"},"PeriodicalIF":1.8,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146155811","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}
Pub Date : 2026-04-01Epub Date: 2026-02-03DOI: 10.1016/j.apradiso.2026.112478
Bruno Araujo, Rene Rocca, Juan Mittani
This study investigates the Optically Stimulated Luminescence (OSL) characteristics of seven distinct color varieties of natural Brazilian quartz to characterize their charge-storage mechanisms relevant to radiation dosimetry. OSL measurements were performed using Blue Stimulated Luminescence (BSL) at 470 nm and Violet Stimulated Luminescence (VSL) at 405 nm. OSL component analysis utilized the Pseudo-Linear Modulation technique to determine the photoionization cross-section (σ) for each resolved trap. The results indicate that the OSL response is highly heterogeneous and dependent on both the sample's coloration and the stimulation wavelength. Crucially, a non-correlation was established between the integrated TL intensity and the OSL signal intensity, suggesting that the charge trap populations accessed by thermal and optical means are not universally shared across all quartz varieties. The VSL method proved superior for trap resolution, consistently detecting one or two more components per sample than BSL, underscoring the shorter wavelength's ability to probe deeper traps. Quantitative analysis confirmed low occupancy of conventional slow traps and, significantly, identified three novel photoionization cross-sections (C3, C6, and C8) unique to these colored mineral quartz samples. Furthermore, for specific components of some colored quartz varieties, the cross-section at 470 nm exceeded that at 405 nm, indicating that photo-eviction efficiency is not strictly monotonically increasing function of photon energy. Instead, it is modulated by the specific trap kinetics and spectral sensitivity inherent to the mineral's impurity-related defect structures.
{"title":"Optically Stimulated Luminescence (OSL) characteristics of seven different color types of quartz samples under 470 and 405 nm stimulation","authors":"Bruno Araujo, Rene Rocca, Juan Mittani","doi":"10.1016/j.apradiso.2026.112478","DOIUrl":"10.1016/j.apradiso.2026.112478","url":null,"abstract":"<div><div>This study investigates the Optically Stimulated Luminescence (OSL) characteristics of seven distinct color varieties of natural Brazilian quartz to characterize their charge-storage mechanisms relevant to radiation dosimetry. OSL measurements were performed using Blue Stimulated Luminescence (BSL) at 470 nm and Violet Stimulated Luminescence (VSL) at 405 nm. OSL component analysis utilized the Pseudo-Linear Modulation technique to determine the photoionization cross-section (σ) for each resolved trap. The results indicate that the OSL response is highly heterogeneous and dependent on both the sample's coloration and the stimulation wavelength. Crucially, a non-correlation was established between the integrated TL intensity and the OSL signal intensity, suggesting that the charge trap populations accessed by thermal and optical means are not universally shared across all quartz varieties. The VSL method proved superior for trap resolution, consistently detecting one or two more components per sample than BSL, underscoring the shorter wavelength's ability to probe deeper traps. Quantitative analysis confirmed low occupancy of conventional slow traps and, significantly, identified three novel photoionization cross-sections (C3, C6, and C8) unique to these colored mineral quartz samples. Furthermore, for specific components of some colored quartz varieties, the cross-section at 470 nm exceeded that at 405 nm, indicating that photo-eviction efficiency is not strictly monotonically increasing function of photon energy. Instead, it is modulated by the specific trap kinetics and spectral sensitivity inherent to the mineral's impurity-related defect structures.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"230 ","pages":"Article 112478"},"PeriodicalIF":1.8,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146155904","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}
Pub Date : 2026-04-01Epub Date: 2026-01-29DOI: 10.1016/j.apradiso.2026.112474
Peng Dang , Ziya Feng , Xiaoyong Yang , Xingjiang Cao , Lanlan Tian , Xiaodong Shi , Xiaolei Shen , Jie Qi , Ende Zhong , Jin Wang
Background
The handling of non-sealed radiopharmaceuticals poses significant risks of occupational exposure and radioactive contamination. With rapid growth in demand, an increasing number of workers are long-term exposed to various radiation hazards. However, the exposure characteristics and dosimetry basics remain poorly understood.
Methods
This study reconstructed 1189 personal dose equivalent data for 311 radiation workers from 2021 to 2023 in China to analyze exposure characteristics. Through on-site inspections of the radiation levels in 15 representative facilities, 1889 measurement points were assessed for radiation hazard distributions and dose contributions. Based on Biological Effects of Ionizing Radiation-VII (BEIR-VII) risk models, 120 exposure scenarios were considered to estimate excess lifetime risks of stochastic effects.
Results
The maximum annual effective dose reaches 5.29 mSv and presents a decreasing trend annually. Some occupational personnel, such as production technicians, should be given more attention regarding radiation exposure. Monitoring of nuclide operational quantities is conducive to avoiding overexposure. Gamma-rays are the largest dose source, contributing more than 75 % of the personal dose, with a maximum dose rate of 50 μSv/h. The dose contribution of neutrons cannot be ignored, particularly for cyclotron operators. The highest lifetime risks of thyroid cancer and leukemia caused by annual doses are 1.8 × 10−5 and 1.03 × 10−5, respectively. The radiological risk also increases with longer working years and higher doses.
Conclusions
It is necessary to strengthen radiation protection for some workers, especially production technicians and cyclotron operators, and conduct radiation monitoring in high-risk workplaces, including hot cells. The radiological risks caused by accumulated dose should not be ignored, particularly during the early career.
{"title":"Evaluation of exposure characteristics and radiological risks for cyclotron-based 18F radiopharmaceutical production workers in China","authors":"Peng Dang , Ziya Feng , Xiaoyong Yang , Xingjiang Cao , Lanlan Tian , Xiaodong Shi , Xiaolei Shen , Jie Qi , Ende Zhong , Jin Wang","doi":"10.1016/j.apradiso.2026.112474","DOIUrl":"10.1016/j.apradiso.2026.112474","url":null,"abstract":"<div><h3>Background</h3><div>The handling of non-sealed radiopharmaceuticals poses significant risks of occupational exposure and radioactive contamination. With rapid growth in demand, an increasing number of workers are long-term exposed to various radiation hazards. However, the exposure characteristics and dosimetry basics remain poorly understood.</div></div><div><h3>Methods</h3><div>This study reconstructed 1189 personal dose equivalent data for 311 radiation workers from 2021 to 2023 in China to analyze exposure characteristics. Through on-site inspections of the radiation levels in 15 representative facilities, 1889 measurement points were assessed for radiation hazard distributions and dose contributions. Based on Biological Effects of Ionizing Radiation-VII (BEIR-VII) risk models, 120 exposure scenarios were considered to estimate excess lifetime risks of stochastic effects.</div></div><div><h3>Results</h3><div>The maximum annual effective dose reaches 5.29 mSv and presents a decreasing trend annually. Some occupational personnel, such as production technicians, should be given more attention regarding radiation exposure. Monitoring of nuclide operational quantities is conducive to avoiding overexposure. Gamma-rays are the largest dose source, contributing more than 75 % of the personal dose, with a maximum dose rate of 50 μSv/h. The dose contribution of neutrons cannot be ignored, particularly for cyclotron operators. The highest lifetime risks of thyroid cancer and leukemia caused by annual doses are 1.8 × 10<sup>−5</sup> and 1.03 × 10<sup>−5</sup>, respectively. The radiological risk also increases with longer working years and higher doses.</div></div><div><h3>Conclusions</h3><div>It is necessary to strengthen radiation protection for some workers, especially production technicians and cyclotron operators, and conduct radiation monitoring in high-risk workplaces, including hot cells. The radiological risks caused by accumulated dose should not be ignored, particularly during the early career.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"230 ","pages":"Article 112474"},"PeriodicalIF":1.8,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146103339","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}
A novel compact Rn-220 reference chamber with stable temperature and humidity control was successfully designed and developed to support radiation-related experimental studies. The device consists of a 200 L cylindrical sealed chamber made of 304 stainless-steel, providing excellent airtightness and corrosion resistance. Concentration levels inside the chamber were tested using both 36 and 9 thorium doped lantern mantles as radioactive sources. A tray containing iodine-free supersaturated salt solution was placed at the bottom to regulate humidity, while a fan positioned at the top ensured adequate air mixing at a circulation rate of 12 m3 min−1. Experimental results indicated that the system could maintain a relative humidity of 73 ± 3%, while the temperature was stabilized at 31 ± 1 °C by an external air-conditioning system. Multi-point monitoring using a RAD7 radon detector indicated that the overall Rn-220 concentrations reached 166,700 ± 35,300 Bq m−3 and 47,700 ± 12,400 Bq m−3. The uncertainty of the 9 thorium doped lantern mantles configuration was 26.0%. Given the small vertical concentration difference across three heights with 9 thorium doped lantern mantles, this configuration was selected as the reference Rn-220 source. This compact Rn-220 reference chamber has potential applicability in instrument calibration and radiation-related studies.
{"title":"A compact Rn-220 reference chamber with constant temperature and humidity","authors":"Hongbo Xu, Zhongkai Fan, Ruomei Xie, Xinyue Yang, Shicheng Luo, Chenxi Zu, Feng Xiao, Xianfa Mao, Hongzhi Yuan, Yanliang Tan","doi":"10.1016/j.apradiso.2026.112477","DOIUrl":"10.1016/j.apradiso.2026.112477","url":null,"abstract":"<div><div>A novel compact Rn-220 reference chamber with stable temperature and humidity control was successfully designed and developed to support radiation-related experimental studies. The device consists of a 200 L cylindrical sealed chamber made of 304 stainless-steel, providing excellent airtightness and corrosion resistance. Concentration levels inside the chamber were tested using both 36 and 9 thorium doped lantern mantles as radioactive sources. A tray containing iodine-free supersaturated salt solution was placed at the bottom to regulate humidity, while a fan positioned at the top ensured adequate air mixing at a circulation rate of 12 m<sup>3</sup> min<sup>−1</sup>. Experimental results indicated that the system could maintain a relative humidity of 73 ± 3%, while the temperature was stabilized at 31 ± 1 °C by an external air-conditioning system. Multi-point monitoring using a RAD7 radon detector indicated that the overall Rn-220 concentrations reached <strong>166,700 ± 35,300 Bq m<sup>−3</sup></strong> and 47,700 ± 12,400 Bq m<sup>−3</sup>. The uncertainty of the 9 thorium doped lantern mantles configuration was 26.0%. Given the small vertical concentration difference across three heights with 9 thorium doped lantern mantles, this configuration was selected as the reference Rn-220 source. This compact Rn-220 reference chamber has potential applicability in instrument calibration and radiation-related studies.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"230 ","pages":"Article 112477"},"PeriodicalIF":1.8,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146123417","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}
This study aims to radiolabel a nanoparticle formulation containing donepezil with Ga-68 radionuclide with high efficiency for diagnosing Alzheimer's disease. In order to develop lipid carrier systems with biocompatible contents in nanoparticle structures, extensive formulation studies were conducted. These systems were subsequently radiolabeled with Ga-68 radionuclide to evaluate their radiolabeling efficiencies. The results are highly encouraging, suggesting that effective radiolabeling is indeed possible. These findings are particularly significant as they open up a range of applications for targeted drug delivery, medical imaging, and diagnostics. Overall, this study represents a valuable contribution to the expanding body of knowledge on lipid carrier systems in healthcare.
Material and method
Nanocarrier formulations were prepared. The radiolabeling parameters of the prepared formulations were studied comparatively. A Ga-68 radionuclide with a half-life of 68 min was used for this. Incubation time, amount of radioactivity, and pH parameters were studied.
Results and discussion
The radiolabeling incubation time, pH of the experimental medium, and amount of radioactivity were tested, and the optimal parameters were identified. According to the results of the radiolabeling studies, optimal radiolabeling with Ga-68 radionuclide was obtained in an acid medium (pH: 5), with a 60 min incubation time, and using 5 mCi of activity in the DOTA-functionalized nanolipid formulations, achieving 89.17 % efficiency. Furthermore, quantitative in vivo PET/CT imaging in nude mice (n = 3/group) demonstrated that the optimized Ga-68-DNP-NLC formulation achieved statistically significant and higher brain uptake compared to the free Ga-68 control, confirming its ability to cross the blood-brain barrier.
{"title":"Development and quality control studies of radiolabelled nanostructured lipid formulations with Ga-68","authors":"Emine Selin Demi̇r, Evren Atlıhan Gündoğdu, Emre Özgenç","doi":"10.1016/j.apradiso.2026.112453","DOIUrl":"10.1016/j.apradiso.2026.112453","url":null,"abstract":"<div><h3>Objective</h3><div>This study aims to radiolabel a nanoparticle formulation containing donepezil with Ga-68 radionuclide with high efficiency for diagnosing Alzheimer's disease. In order to develop lipid carrier systems with biocompatible contents in nanoparticle structures, extensive formulation studies were conducted. These systems were subsequently radiolabeled with Ga-68 radionuclide to evaluate their radiolabeling efficiencies. The results are highly encouraging, suggesting that effective radiolabeling is indeed possible. These findings are particularly significant as they open up a range of applications for targeted drug delivery, medical imaging, and diagnostics. Overall, this study represents a valuable contribution to the expanding body of knowledge on lipid carrier systems in healthcare.</div></div><div><h3>Material and method</h3><div>Nanocarrier formulations were prepared. The radiolabeling parameters of the prepared formulations were studied comparatively. A Ga-68 radionuclide with a half-life of 68 min was used for this. Incubation time, amount of radioactivity, and pH parameters were studied.</div></div><div><h3>Results and discussion</h3><div>The radiolabeling incubation time, pH of the experimental medium, and amount of radioactivity were tested, and the optimal parameters were identified. According to the results of the radiolabeling studies, optimal radiolabeling with Ga-68 radionuclide was obtained in an acid medium (pH: 5), with a 60 min incubation time, and using 5 mCi of activity in the DOTA-functionalized nanolipid formulations, achieving 89.17 % efficiency. Furthermore, quantitative in vivo PET/CT imaging in nude mice (n = 3/group) demonstrated that the optimized Ga-68-DNP-NLC formulation achieved statistically significant and higher brain uptake compared to the free Ga-68 control, confirming its ability to cross the blood-brain barrier.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"230 ","pages":"Article 112453"},"PeriodicalIF":1.8,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146016963","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}
This study investigated the effects of anti-scatter grid removal on radiation dose, image quality, and anatomical visibility in lateral (LAT) cervical spine imaging.
Methods
A two-part prospective study was conducted. In the phantom study, an anthropomorphic head-torso phantom with lard simulating extra fatty tissue of 2–10 cm in 2 cm increments was imaged using protocols with and without an anti-scatter grid. In the clinical study, 80 patients were randomly divided into two groups: half were imaged with an anti-scatter grid, and half without. Data collected included gender, body mass index (BMI), Dose Area Product (DAP), tube voltage (kV), current-time product (mAs), filtration, neck width, and use of Automatic Exposure Control (AEC). Effective dose (ED) and dose to selected organs were calculated using PCXMC 2.0 software. Two traumatologists and one radiologist evaluated all phantom and patient images according to European guidelines using a four-point scale (1 = diagnostically inadequate image; 4 = excellent image quality).
Results
In the phantom study, removal of the anti-scatter grid reduced mean DAP by 52.1 % (p < 0.001) without affecting diagnostic adequacy; soft tissue-bone contrast improved (p = 0.009). In the patient study, removal of the anti-scatter grid reduced mean DAP and ED by 63.1 % and 61.7 %, respectively (both p < 0.001). All organ doses were significantly lower (p < 0.001). Soft tissue visibility improved by 12.5 % (p = 0.011), and soft tissue-bone contrast improved by 9.1 % (p = 0.007) without the anti-scatter grid. No other quality criteria differed significantly.
Conclusion
In both phantom and patient studies, removal of the anti-scatter grid resulted in significant dose reduction while maintaining or improving image quality. These results are consistent with previous findings and support the As Low As Reasonably Achievable (ALARA) principle. Omitting the anti-scatter grid in LAT cervical spine imaging reduces dose by about 60 % without compromising diagnostic quality. Routine use in clinical practice is recommended to increase patient safety.
{"title":"Comparative analysis of lateral cervical radiographic imaging quality with and without anti-scatter grid application","authors":"Daša Lučić , Laura Jurša , Erna Alukić , Nejc Mekiš","doi":"10.1016/j.apradiso.2026.112459","DOIUrl":"10.1016/j.apradiso.2026.112459","url":null,"abstract":"<div><h3>Purpose</h3><div>This study investigated the effects of anti-scatter grid removal on radiation dose, image quality, and anatomical visibility in lateral (LAT) cervical spine imaging.</div></div><div><h3>Methods</h3><div>A two-part prospective study was conducted. In the phantom study, an anthropomorphic head-torso phantom with lard simulating extra fatty tissue of 2–10 cm in 2 cm increments was imaged using protocols with and without an anti-scatter grid. In the clinical study, 80 patients were randomly divided into two groups: half were imaged with an anti-scatter grid, and half without. Data collected included gender, body mass index (BMI), Dose Area Product (DAP), tube voltage (kV), current-time product (mAs), filtration, neck width, and use of Automatic Exposure Control (AEC). Effective dose (ED) and dose to selected organs were calculated using PCXMC 2.0 software. Two traumatologists and one radiologist evaluated all phantom and patient images according to European guidelines using a four-point scale (1 = diagnostically inadequate image; 4 = excellent image quality).</div></div><div><h3>Results</h3><div>In the phantom study, removal of the anti-scatter grid reduced mean DAP by 52.1 % (p < 0.001) without affecting diagnostic adequacy; soft tissue-bone contrast improved (p = 0.009). In the patient study, removal of the anti-scatter grid reduced mean DAP and ED by 63.1 % and 61.7 %, respectively (both p < 0.001). All organ doses were significantly lower (p < 0.001). Soft tissue visibility improved by 12.5 % (p = 0.011), and soft tissue-bone contrast improved by 9.1 % (p = 0.007) without the anti-scatter grid. No other quality criteria differed significantly.</div></div><div><h3>Conclusion</h3><div>In both phantom and patient studies, removal of the anti-scatter grid resulted in significant dose reduction while maintaining or improving image quality. These results are consistent with previous findings and support the As Low As Reasonably Achievable (ALARA) principle. Omitting the anti-scatter grid in LAT cervical spine imaging reduces dose by about 60 % without compromising diagnostic quality. Routine use in clinical practice is recommended to increase patient safety.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"230 ","pages":"Article 112459"},"PeriodicalIF":1.8,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146074872","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}
The purpose of this study is to evaluate the level of radon in tap water and its associated health impacts in Mueang District, Ubon Ratchathani Province, Thailand. The condition focuses on the annual effective dose (AED), excess lifetime cancer risk (ELCR), and lung cancer cases per year per million persons (LCC) in different age groups, including infants (0–1 year old), children (2–17 years old), and adults (above 17 years old). A total of 27 samples is collected from different areas of Ubon Ratchathani, and the measurement is done with the RAD7 radon detector and accessories of RAD H2O. The average radon level in tap water in Ubon Ratchathani is at 0.40 ± 0.09 Bq/L, which is quite lower as compared to the guideline value suggested by the United States Environmental Protection Agency (US EPA). It should be noted that the measured values are close to the detection limit of the RAD7 & H2O system, and the uncertainty at such low concentrations is relatively high. The annual effective dose, excess lifetime cancer risks, and lung cancer cases per year per million persons vary among each age group. Infants have the highest average annual effective dose, followed by adults and children, of 2.13 ± 0.48 μSv/y, 0.78 ± 0.18 μSv/y, and 1.03 ± 0.23 μSv/y, respectively. A similar trend is also found in excess lifetime cancer risk and lung cancer cases per year per million persons. This finding shows that the radon level in the tap water in the area of study is lower than the level recommended by the World Health Organization (WHO); however, continuous monitoring is required to prevent health risks for the population.
{"title":"Age-specific assessment of annual effective dose and excess lifetime cancer risk from radon in tap water of Mueang Ubon Ratchathani, Thailand","authors":"Ing-orn Sittitanadol , Khanuengnij Prakhammin , Junthara Somtua , Vitsanusat Atyotha","doi":"10.1016/j.apradiso.2026.112455","DOIUrl":"10.1016/j.apradiso.2026.112455","url":null,"abstract":"<div><div>The purpose of this study is to evaluate the level of radon in tap water and its associated health impacts in Mueang District, Ubon Ratchathani Province, Thailand. The condition focuses on the annual effective dose (AED), excess lifetime cancer risk (ELCR), and lung cancer cases per year per million persons (LCC) in different age groups, including infants (0–1 year old), children (2–17 years old), and adults (above 17 years old). A total of 27 samples is collected from different areas of Ubon Ratchathani, and the measurement is done with the RAD7 radon detector and accessories of RAD H<sub>2</sub>O. The average radon level in tap water in Ubon Ratchathani is at 0.40 ± 0.09 Bq/L, which is quite lower as compared to the guideline value suggested by the United States Environmental Protection Agency (US EPA). It should be noted that the measured values are close to the detection limit of the RAD7 & H<sub>2</sub>O system, and the uncertainty at such low concentrations is relatively high. The annual effective dose, excess lifetime cancer risks, and lung cancer cases per year per million persons vary among each age group. Infants have the highest average annual effective dose, followed by adults and children, of 2.13 ± 0.48 μSv/y, 0.78 ± 0.18 μSv/y, and 1.03 ± 0.23 μSv/y, respectively. A similar trend is also found in excess lifetime cancer risk and lung cancer cases per year per million persons. This finding shows that the radon level in the tap water in the area of study is lower than the level recommended by the World Health Organization (WHO); however, continuous monitoring is required to prevent health risks for the population.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"230 ","pages":"Article 112455"},"PeriodicalIF":1.8,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146036114","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}
Neptunium-236g (236gNp) has been focused as a candidate spike for the mass spectrometry of 237Np which is a long-lived anthropogenic radionuclide present in the environment. In order to evaluate the feasibility of synthesising 236Np, experiments were conducted to detect and quantify the by-product 234Np and the nuclear isomer 236mNp produced in the nuclear reaction by irradiating 232Th with 7Li. First, the chemical separation method was developed for the ultra-trace amounts of Np produced from the main matrix of Th and from the fission-derived nuclides and Pa isotopes produced by side reactions, based on using two solid-phase extraction resins. As a result of applying the constructed separation scheme to irradiated Th foils and Th electrodeposited samples at the AVF Cyclotron of the RIKEN RI Beam Factory (Japan), 236mNp was successfully detected in the 232Th+7Li system for the first time. Based on experiments with 232Th irradiated at 7Li beam energies of ca.29 MeV–42 MeV, the nuclear reaction cross sections for the production of 236mNp were found to be in the range 0.12–0.39 mb. This finding indicated that the spike candidate 236gNp was also produced by the proposed nuclear reactions.
{"title":"Investigation toward the production of 236gNp via the 232Th + 7Li reaction: Synthesis of 236mNp and 234Np","authors":"Akihisa Nakajima , Yuta Hayakawa , Ayumu Nagai , Akihiko Yokoyama , Hiromitsu Haba , Yukiko Komori , Takuya Yokokita , Yuma Sakakieda , Keisuke Sueki , Shinya Yamasaki , Aya Sakaguchi","doi":"10.1016/j.apradiso.2025.112397","DOIUrl":"10.1016/j.apradiso.2025.112397","url":null,"abstract":"<div><div>Neptunium-236g (<sup>236g</sup>Np) has been focused as a candidate spike for the mass spectrometry of <sup>237</sup>Np which is a long-lived anthropogenic radionuclide present in the environment. In order to evaluate the feasibility of synthesising <sup>236</sup>Np, experiments were conducted to detect and quantify the by-product <sup>234</sup>Np and the nuclear isomer <sup>236m</sup>Np produced in the nuclear reaction by irradiating <sup>232</sup>Th with <sup>7</sup>Li. First, the chemical separation method was developed for the ultra-trace amounts of Np produced from the main matrix of Th and from the fission-derived nuclides and Pa isotopes produced by side reactions, based on using two solid-phase extraction resins. As a result of applying the constructed separation scheme to irradiated Th foils and Th electrodeposited samples at the AVF Cyclotron of the RIKEN RI Beam Factory (Japan), <sup>236m</sup>Np was successfully detected in the <sup>232</sup>Th+<sup>7</sup>Li system for the first time. Based on experiments with <sup>232</sup>Th irradiated at <sup>7</sup>Li beam energies of ca.29 MeV–42 MeV, the nuclear reaction cross sections for the production of <sup>236m</sup>Np were found to be in the range 0.12–0.39 mb. This finding indicated that the spike candidate <sup>236g</sup>Np was also produced by the proposed nuclear reactions.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"230 ","pages":"Article 112397"},"PeriodicalIF":1.8,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145969404","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}
An appropriate target system is crucial for converting the incident proton beam from a cyclotron into a neutron beam, which drives a subcritical reactor in a small-scale accelerator-driven system (SS-ADS). The methodology for designing the target system was a combination of the Particle and Heavy Ion code Transport System (PHITS) simulation and the Response Surface Methodology (RSM) analysis. PHITS simulations applied the proton beam specifications from the DECY-13 cyclotron as the particle source model, and RSM incorporated the external neutron beam requirement of the SAMOP subcritical reactor into the optimization. Beryllium was chosen as the target material because it produces the highest neutron yield per incident proton, outperforming other candidates such as manganese, titanium, and vanadium. The heavy water moderated neutrons produced by the 9Be(p,n)9B reaction, while polyethylene functioned as a neutron reflector. The analysis result shows that the optimal target system consisted of the target material in a form of obstructed needle with radial thickness of 0.18 cm, cavity length of 2.56 cm, obstructed thickness and angle of 0.17 cm and 31.06 degree; the moderator in a shape of truncated cone with length of 3.26 cm, entrance and exit radius of 0.85 cm and 0.91 cm; and neutron reflector thickness 15.64 cm. Equipped with the target system, the DECY-13 cyclotron can deliver a thermal neutron flux of (2.7 ± 0.1)×108 n/cm2s, sufficient to drive the SS-ADS subcritical reactor. An additional PHITS simulation with the optimal configuration validated the RSM prediction by producing a thermal neutron flux of (2.81 ± 0.02)×108 n/cm2s. It indicates that RSM prediction is highly accurate in this case, with a deviation of 3.91 %.
{"title":"Design analysis of neutron source based on low energy cyclotron used for small-scale accelerator-driven system","authors":"Syarip Syarip , Isdandy Rezki Febrianto , Djoko Slamet Pudjorahardjo , Taufik , Wijono , Aniti Payudan , Andang Widi Harto","doi":"10.1016/j.apradiso.2026.112473","DOIUrl":"10.1016/j.apradiso.2026.112473","url":null,"abstract":"<div><div>An appropriate target system is crucial for converting the incident proton beam from a cyclotron into a neutron beam, which drives a subcritical reactor in a small-scale accelerator-driven system (SS-ADS). The methodology for designing the target system was a combination of the Particle and Heavy Ion code Transport System (PHITS) simulation and the Response Surface Methodology (RSM) analysis. PHITS simulations applied the proton beam specifications from the DECY-13 cyclotron as the particle source model, and RSM incorporated the external neutron beam requirement of the SAMOP subcritical reactor into the optimization. Beryllium was chosen as the target material because it produces the highest neutron yield per incident proton, outperforming other candidates such as manganese, titanium, and vanadium. The heavy water moderated neutrons produced by the <sup>9</sup>Be(p,n)<sup>9</sup>B reaction, while polyethylene functioned as a neutron reflector. The analysis result shows that the optimal target system consisted of the target material in a form of obstructed needle with radial thickness of 0.18 cm, cavity length of 2.56 cm, obstructed thickness and angle of 0.17 cm and 31.06 degree; the moderator in a shape of truncated cone with length of 3.26 cm, entrance and exit radius of 0.85 cm and 0.91 cm; and neutron reflector thickness 15.64 cm. Equipped with the target system, the DECY-13 cyclotron can deliver a thermal neutron flux of (2.7 ± 0.1)×10<sup>8</sup> n/cm<sup>2</sup>s, sufficient to drive the SS-ADS subcritical reactor. An additional PHITS simulation with the optimal configuration validated the RSM prediction by producing a thermal neutron flux of (2.81 ± 0.02)×10<sup>8</sup> n/cm<sup>2</sup>s. It indicates that RSM prediction is highly accurate in this case, with a deviation of 3.91 %.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"230 ","pages":"Article 112473"},"PeriodicalIF":1.8,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146111600","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}
Pub Date : 2026-04-01Epub Date: 2026-01-31DOI: 10.1016/j.apradiso.2026.112463
M. Sankari, M.V. Suryanarayana
We have theoretically studied the laser isotope separation of 169Yb from irradiated natural Yb through three-step laser photoionization process. The optimal configuration of the laser isotope separation system for enriching 169Yb has been determined by applying the density matrix formalism to the laser-atom interactions in a three-step photoionization process. It has been shown that it is possible to produce 63.1% enriched 169Yb at a production rate of 4.2 μg/hour (or 100 μg/day) which corresponds to 2.4 Ci/day from the natural Yb irradiated in low flux reactors. Employing the derived configuration, it is possible to produce one to two orders higher activity of 169Yb from natural Yb irradiated in medium or high flux reactors respectively. This is the first ever study on the laser isotope separation of 169Yb.
{"title":"Theoretical assessment of laser isotope separation for the production of high-specific-activity 169Yb from irradiated natural ytterbium","authors":"M. Sankari, M.V. Suryanarayana","doi":"10.1016/j.apradiso.2026.112463","DOIUrl":"10.1016/j.apradiso.2026.112463","url":null,"abstract":"<div><div>We have theoretically studied the laser isotope separation of <sup>169</sup>Yb from irradiated natural Yb through three-step laser photoionization process. The optimal configuration of the laser isotope separation system for enriching <sup>169</sup>Yb has been determined by applying the density matrix formalism to the laser-atom interactions in a three-step photoionization process. It has been shown that it is possible to produce 63.1% enriched <sup>169</sup>Yb at a production rate of 4.2 μg/hour (or 100 μg/day) which corresponds to 2.4 Ci/day from the natural Yb irradiated in low flux reactors. Employing the derived configuration, it is possible to produce one to two orders higher activity of <sup>169</sup>Yb from natural Yb irradiated in medium or high flux reactors respectively. This is the first ever study on the laser isotope separation of <sup>169</sup>Yb.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"230 ","pages":"Article 112463"},"PeriodicalIF":1.8,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146130705","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}
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