Pub Date : 2025-12-15DOI: 10.1016/j.apradiso.2025.112379
Fatma Tuba Çoğalmış , Deniz Agehan Kahraman , Dilek Küçüklü , Ayse Nur Esen , Bahire Filiz Şenkal , Gülin Selda Pozan Soylu , Sevilay Haciyakupoglu , Ahmet Durmayaz , İskender Atilla Reyhancan , Ömer Şahin , Caner Ünlü
This study investigated lead-free newly produced polyaniline composites, doped with different concentrations of bismuth vanadate (BiVO4) (10–20 wt%) without disrupting the polyaniline structure, and explored the potential of these composites as an effective gamma-ray shielding material for the first time. Linear and mass attenuation coefficients (LAC, MAC), half- and tenth-value layers (HVL, TVL), mean free paths (MFP), and radiation shielding efficiencies of composites at low and medium gamma-ray energies were analyzed experimentally. It was observed that with increasing BiVO4 concentration, MAC and LAC values increased at different ratios, and HVL, TVL and MFP values decreased at different ratios, for gamma rays with different energies. An increase in BiVO4 concentration led to a substantial enhancement in the LAC, rising from 0.14 to 0.75 cm−1 at low gamma-ray energy (59.5 keV). In contrast, only a slight increase in the LAC was observed at medium gamma-ray energy (662 keV). Moreover, HVL decreased by approximately 81 % at 59.5 keV and by 25 % at 662 keV. The composite with 20 wt% BiVO4 sample was the best gamma-ray attenuator among all produced composites. Overall, this research highlights the potential of BiVO4-doped polymer composites as efficient and promising materials for shielding low and medium energy gamma-rays in various fields, including industrial and medical radiation facilities, offering a hopeful outlook for the future of radiation protection.
{"title":"A lead-free alternative for gamma-ray shielding: Newly developed BiVO4-doped polyaniline composites","authors":"Fatma Tuba Çoğalmış , Deniz Agehan Kahraman , Dilek Küçüklü , Ayse Nur Esen , Bahire Filiz Şenkal , Gülin Selda Pozan Soylu , Sevilay Haciyakupoglu , Ahmet Durmayaz , İskender Atilla Reyhancan , Ömer Şahin , Caner Ünlü","doi":"10.1016/j.apradiso.2025.112379","DOIUrl":"10.1016/j.apradiso.2025.112379","url":null,"abstract":"<div><div>This study investigated lead-free newly produced polyaniline composites, doped with different concentrations of bismuth vanadate (BiVO<sub>4</sub>) (10–20 wt%) without disrupting the polyaniline structure, and explored the potential of these composites as an effective gamma-ray shielding material for the first time. Linear and mass attenuation coefficients (LAC, MAC), half- and tenth-value layers (HVL, TVL), mean free paths (MFP), and radiation shielding efficiencies of composites at low and medium gamma-ray energies were analyzed experimentally. It was observed that with increasing BiVO<sub>4</sub> concentration, MAC and LAC values increased at different ratios, and HVL, TVL and MFP values decreased at different ratios, for gamma rays with different energies. An increase in BiVO<sub>4</sub> concentration led to a substantial enhancement in the LAC, rising from 0.14 to 0.75 cm<sup>−1</sup> at low gamma-ray energy (59.5 keV). In contrast, only a slight increase in the LAC was observed at medium gamma-ray energy (662 keV). Moreover, HVL decreased by approximately 81 % at 59.5 keV and by 25 % at 662 keV. The composite with 20 wt% BiVO<sub>4</sub> sample was the best gamma-ray attenuator among all produced composites. Overall, this research highlights the potential of BiVO<sub>4</sub>-doped polymer composites as efficient and promising materials for shielding low and medium energy gamma-rays in various fields, including industrial and medical radiation facilities, offering a hopeful outlook for the future of radiation protection.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112379"},"PeriodicalIF":1.8,"publicationDate":"2025-12-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787206","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}
is an Auger emitting radionuclide which may have therapeutic potential, particularly when labeled to the chemotherapeutic drug cisplatin. One challenge to broader explorations of its clinical potential is the need for production routes with high specific activity. As part of a larger campaign to address gaps in reaction data for emerging medical radionuclides, this work seeks to characterize the (d,x) reactions as a potential production pathway for . A stacked target irradiation, consisting of natural iridium, iron, nickel, and copper foils, was performed using a 33 MeV deuteron beam at the Lawrence Berkeley National Laboratory 88-Inch Cyclotron. This measurement, along with previous experimental data, suggests an energy window between 11 to 18 MeV to maximize the production and radiopurity of . This experiment has yielded cross sections for 43 channels of deuteron-induced reactions from threshold to 30 MeV, including the first experimental results of (d,x) (cumulative), (d,x) (independent), (d,x) (cumulative) and (d,x) , (cumulative). The results were compared with literature data, the TENDL-2023 database, and default theoretical calculations from the TALYS-2.04, CoH-3.6.0, EMPIRE-3.2.3, and ALICE-2020 reaction modeling codes. This work presents another example of the lack of predictive capabilities for this set of modern nuclear-reaction modeling codes, and highlights the unsatisfactory modeling of experimental cross sections. Experimental data are important to improve the codes in general, and new experimental results can be used to improve the models. Finally, this measurement has revealed the need for an updated evaluation of the (d,x) deuteron monitor reaction.
{"title":"Nuclear excitation functions for medical isotope production: Targeted radionuclide therapy via natIr(d,x)193mPt","authors":"H.L.O. Ekeberg , A.S. Voyles , M.S. Basunia , J.C. Batchelder , L.A. Bernstein , D.L. Bleuel , K.C.W. Li , E.M. Martinsen , E.F. Matthews , J.T. Morrell , N.I.J. Pettersen , S. Siem","doi":"10.1016/j.apradiso.2025.112311","DOIUrl":"10.1016/j.apradiso.2025.112311","url":null,"abstract":"<div><div><figure><img></figure> is an Auger emitting radionuclide which may have therapeutic potential, particularly when labeled to the chemotherapeutic drug cisplatin. One challenge to broader explorations of its clinical potential is the need for production routes with high specific activity. As part of a larger campaign to address gaps in reaction data for emerging medical radionuclides, this work seeks to characterize the <figure><img></figure> (d,x) reactions as a potential production pathway for <figure><img></figure> . A stacked target irradiation, consisting of natural iridium, iron, nickel, and copper foils, was performed using a 33 MeV deuteron beam at the Lawrence Berkeley National Laboratory 88-Inch Cyclotron. This measurement, along with previous experimental data, suggests an energy window between 11 to 18 MeV to maximize the production and radiopurity of <figure><img></figure> . This experiment has yielded cross sections for 43 channels of deuteron-induced reactions from threshold to 30 MeV, including the first experimental results of <figure><img></figure> (d,x) <figure><img></figure> (cumulative), <figure><img></figure> (d,x) <figure><img></figure> (independent), <figure><img></figure> (d,x) <figure><img></figure> (cumulative) and <figure><img></figure> (d,x) <figure><img></figure> , <figure><img></figure> (cumulative). The results were compared with literature data, the TENDL-2023 database, and default theoretical calculations from the <span>TALYS-2.04</span>, <span>CoH-3.6.0</span>, <span>EMPIRE-3.2.3</span>, and <span>ALICE-2020</span> reaction modeling codes. This work presents another example of the lack of predictive capabilities for this set of modern nuclear-reaction modeling codes, and highlights the unsatisfactory modeling of experimental cross sections. Experimental data are important to improve the codes in general, and new experimental results can be used to improve the models. Finally, this measurement has revealed the need for an updated evaluation of the <figure><img></figure> (d,x) <figure><img></figure> deuteron monitor reaction.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112311"},"PeriodicalIF":1.8,"publicationDate":"2025-12-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145826864","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 : 2025-12-12DOI: 10.1016/j.apradiso.2025.112374
G. Poludniowski, A. Omar
SpekPy is a software toolkit for the Python programming language and designed for modelling X-ray tube spectra. The tookit is used in industry, higher education and research around the world. Previously SpekPy has only had the capability for modelling so-called ‘reflection’ geometry X-ray tubes with thick target anodes consisting of the elements Mo, Rh or W. This work describes extensions in release v2.5 to include four new target elements – Cr, Cu, Ag and Au – as well as modifications to model transmission targets. Predictions for a variety of tubes were compared to results from simulations using the PENELOPE general-purpose Monte Carlo code system and to experimental spectra provided by a manufacturer. Agreement was excellent. If the target thickness was greater than 20% of the continuous slowing down approximation range for the material, the predicted total fluence was within 10% of Monte Carlo results and the discrepancy in spectral shape was negligible. Agreement with experimental spectra was also encouraging. The described advances will permit more types of X-ray tubes to be modelled by SpekPy, extending its usefulness to scientists in a broader range of applications.
{"title":"The SpekPy toolkit for modelling X-ray tube spectra: Extension to transmission targets and additional target materials","authors":"G. Poludniowski, A. Omar","doi":"10.1016/j.apradiso.2025.112374","DOIUrl":"10.1016/j.apradiso.2025.112374","url":null,"abstract":"<div><div>SpekPy is a software toolkit for the Python programming language and designed for modelling X-ray tube spectra. The tookit is used in industry, higher education and research around the world. Previously SpekPy has only had the capability for modelling so-called ‘reflection’ geometry X-ray tubes with thick target anodes consisting of the elements Mo, Rh or W. This work describes extensions in release v2.5 to include four new target elements – Cr, Cu, Ag and Au – as well as modifications to model transmission targets. Predictions for a variety of tubes were compared to results from simulations using the PENELOPE general-purpose Monte Carlo code system and to experimental spectra provided by a manufacturer. Agreement was excellent. If the target thickness was greater than 20% of the continuous slowing down approximation range for the material, the predicted total fluence was within 10% of Monte Carlo results and the discrepancy in spectral shape was negligible. Agreement with experimental spectra was also encouraging. The described advances will permit more types of X-ray tubes to be modelled by SpekPy, extending its usefulness to scientists in a broader range of applications.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112374"},"PeriodicalIF":1.8,"publicationDate":"2025-12-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145767124","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}
Groundwater quality is an important concern for public health, particularly with respect to uranium contamination, which may contribute to radiation dose and chemical toxicity when used for drinking. An analysis of radiation levels in groundwater has been undertaken around Noida, Uttar Pradesh, India, using the LED Fluorimetry Technique. The concentration of uranium (U-238) in water samples obtained from submersible pumps, tube wells, and hand pumps in Noida is determined. The uranium concentration, averaging 10.62 μg L−1, along with the annual effective dose of 1.77 μSv y−1, falls within the safety thresholds recommended by the World Health Organization (2004) and the Atomic Energy Regulatory Board (2004). The chemical toxicity and radiological impact of uranium in water have been assessed. To estimate radiation risks from natural radionuclides in groundwater, radiological health parameters were determined. Elevated activity levels of natural radionuclides in certain areas are attributed to factors such as regional geology, hydrology, and the nature of local industries.
{"title":"Risk assessment of uranium in groundwater surrounding the Greater Noida industrial area, Uttar Pradesh, India","authors":"Narender Singh , Sreejan Rayhan , Amanjeet Panghal , Rekha Dhiman , Navish Kataria , Suneel Kumar , Ranjeet Singh , Balvinder Singh , Lalit Saini","doi":"10.1016/j.apradiso.2025.112376","DOIUrl":"10.1016/j.apradiso.2025.112376","url":null,"abstract":"<div><div>Groundwater quality is an important concern for public health, particularly with respect to uranium contamination, which may contribute to radiation dose and chemical toxicity when used for drinking. An analysis of radiation levels in groundwater has been undertaken around Noida, Uttar Pradesh, India, using the LED Fluorimetry Technique. The concentration of uranium (U-238) in water samples obtained from submersible pumps, tube wells, and hand pumps in Noida is determined. The uranium concentration, averaging 10.62 μg L<sup><em>−1</em></sup>, along with the annual effective dose of 1.77 μSv y<sup><em>−</em>1</sup>, falls within the safety thresholds recommended by the World Health Organization (2004) and the Atomic Energy Regulatory Board (2004). The chemical toxicity and radiological impact of uranium in water have been assessed. To estimate radiation risks from natural radionuclides in groundwater, radiological health parameters were determined. Elevated activity levels of natural radionuclides in certain areas are attributed to factors such as regional geology, hydrology, and the nature of local industries.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112376"},"PeriodicalIF":1.8,"publicationDate":"2025-12-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787270","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 : 2025-12-11DOI: 10.1016/j.apradiso.2025.112373
Zongbiao Liu , Cong Zhou , Siyu Lu , Mingliang Ma , Yun Li , Tongxin Jiang , Na Wang , Haisheng San , Xin Shang
To improve the low energy-conversion efficiency of betavoltaic cells, we design a microscale nano conversion architecture comprising wide-bandgap titanium dioxide (TiO2) nanorod arrays (TNRAs) coupled with lead sulfide (PbS)/zinc sulfide (ZnS) quantum dots (QDs). We develop a composite energy deposition (ED) model and use Monte Carlo (MC) simulations to resolve β-particle scattering within the TNRAs-QD heterostructure. By systematically varying nanorod spacing, QD material, and QD thickness, we find that ZnS QDs incur 21.5 eV less energy loss than PbS QDs, attributable to their higher molecular density ( = 5.06 × 1022 cm−3) and lower mean ionization energy. Differences in differential scattering cross-sections (PbS: 1.62 × 10−19 cm2/sr; ZnS: 3.57 × 10−20 cm2/sr) and scattering probabilities (:∼80 %; :∼63 %) further indicate that ZnS optimizes scattering to enhance electron-hole pair generation. The ZnS-integrated structure achieves a maximum ED rate of 77.24 %, a 13.88 percentage-point improvement over unmodified TNRAs, enabled by extended β-particle migration via multistage scattering. These results provide MC-based design guidance for optimizing TiO2-based betavoltaics and advancing radiation-driven energy harvesting.
{"title":"Energy deposition mechanisms of PbS/ZnS quantum dots in TiO2 nanorod arrays betavoltaic cells","authors":"Zongbiao Liu , Cong Zhou , Siyu Lu , Mingliang Ma , Yun Li , Tongxin Jiang , Na Wang , Haisheng San , Xin Shang","doi":"10.1016/j.apradiso.2025.112373","DOIUrl":"10.1016/j.apradiso.2025.112373","url":null,"abstract":"<div><div>To improve the low energy-conversion efficiency of betavoltaic cells, we design a microscale nano conversion architecture comprising wide-bandgap titanium dioxide (TiO<sub>2</sub>) nanorod arrays (TNRAs) coupled with lead sulfide (PbS)/zinc sulfide (ZnS) quantum dots (QDs). We develop a composite energy deposition (ED) model and use Monte Carlo (MC) simulations to resolve β-particle scattering within the TNRAs-QD heterostructure. By systematically varying nanorod spacing, QD material, and QD thickness, we find that ZnS QDs incur 21.5 eV less energy loss than PbS QDs, attributable to their higher molecular density (<span><math><mrow><mi>N</mi></mrow></math></span> = 5.06 × 10<sup>22</sup> cm<sup>−3</sup>) and lower mean ionization energy. Differences in differential scattering cross-sections (PbS: 1.62 × 10<sup>−19</sup> cm<sup>2</sup>/sr; ZnS: 3.57 × 10<sup>−20</sup> cm<sup>2</sup>/sr) and scattering probabilities (<span><math><mrow><msub><mi>P</mi><mrow><mi>P</mi><mi>b</mi><mi>S</mi></mrow></msub></mrow></math></span>:∼80 %; <span><math><mrow><msub><mi>P</mi><mrow><mi>Z</mi><mi>n</mi><mi>S</mi></mrow></msub></mrow></math></span>:∼63 %) further indicate that ZnS optimizes scattering to enhance electron-hole pair generation. The ZnS-integrated structure achieves a maximum ED rate of 77.24 %, a 13.88 percentage-point improvement over unmodified TNRAs, enabled by extended β-particle migration via multistage scattering. These results provide MC-based design guidance for optimizing TiO<sub>2</sub>-based betavoltaics and advancing radiation-driven energy harvesting.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112373"},"PeriodicalIF":1.8,"publicationDate":"2025-12-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787264","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 : 2025-12-10DOI: 10.1016/j.apradiso.2025.112371
Hiroki Murata , Yuya Soeta , Takahiro Yamada
Self-absorption correction factors for 210Pb and 137Cs were experimentally determined through an intercomparison study. Three different matrix samples provided for the intercomparison test were analyzed. The linear attenuation coefficients for three matrices were measured using point sources of 210Pb and 137Cs without a collimator, with all measurements performed using an N-type coaxial HPGe-detector. To account for the oblique transmission of γ-rays within the samples, effective thickness values were calculated and incorporated into the correction of γ-rays within the calculations. Additionally, a Monte-Carlo simulation was performed using the PHITS code to evaluate the contribution of scattered photons to the full-energy peak. Consequently, the density-dependent quantitative contributions of scattered γ-rays to the full-energy peak areas were determined.
{"title":"Determination of self-absorption correction in the activity measurement of 210Pb","authors":"Hiroki Murata , Yuya Soeta , Takahiro Yamada","doi":"10.1016/j.apradiso.2025.112371","DOIUrl":"10.1016/j.apradiso.2025.112371","url":null,"abstract":"<div><div>Self-absorption correction factors for <sup>210</sup>Pb and <sup>137</sup>Cs were experimentally determined through an intercomparison study. Three different matrix samples provided for the intercomparison test were analyzed. The linear attenuation coefficients for three matrices were measured using point sources of <sup>210</sup>Pb and <sup>137</sup>Cs without a collimator, with all measurements performed using an N-type coaxial HPGe-detector. To account for the oblique transmission of γ-rays within the samples, effective thickness values were calculated and incorporated into the correction of γ-rays within the calculations. Additionally, a Monte-Carlo simulation was performed using the PHITS code to evaluate the contribution of scattered photons to the full-energy peak. Consequently, the density-dependent quantitative contributions of scattered γ-rays to the full-energy peak areas were determined.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112371"},"PeriodicalIF":1.8,"publicationDate":"2025-12-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145733562","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}
Medical imaging is a major source of ionizing radiation exposure in healthcare. Effective radiation protection relies not only on facility design but also on healthcare staff knowledge, attitudes, and practices (KAP). Objective: To evaluate KAP related to radiation protection among staff at two nuclear medicine facilities such as Facility A and Facility B in Addis Ababa, Ethiopia, and assess relationships with occupational exposure and facility design.
Methods
A cross-sectional study was conducted among 28 personnel using structured questionnaires, checklists, and interviews. KAP scores were calculated, with thresholds for satisfactory performance defined as ≥67 % for knowledge, attitude (corrected for misconceptions), and practice. Occupational doses were measured and compared with ICRP limits.
Results
Eighty-five point seven percent of participants demonstrated satisfactory knowledge, while only 64.3 % had a good attitude after correcting misconceptions, such as the incorrect belief that dosimeters prevent all radiation. Seventy-five percent of personnel followed adequate radiation protection practices. The mean annual occupational dose was 0.33 ± 0.13 mSv, significantly below the ICRP limit of 20 mSv/year, indicating low actual exposure despite some gaps in understanding. Although education and occupation influenced practice, no statistically significant associations were found with overall knowledge, attitude, and practice (KAP) scores.
Conclusion
While personnel show adequate knowledge and practice, critical misconceptions about dosimeter function remain. Continuous training and education are necessary to correct these misconceptions. Occupational exposure levels are low, but improved safety culture and awareness are needed to maintain long-term protection. Future research should explore correlations between individual KAP scores and dose readings.
{"title":"Assessment of radiation protection against knowledge, attitude and practice in nuclear medicine facilities in Addis Ababa, Ethiopia","authors":"Mekonnen Tefera Kebede, Jemal Edris Dawud, Bogalech Tiefu Kejela, Metekiya Paulos Gannamo, Yohanse Jemera Mammo","doi":"10.1016/j.apradiso.2025.112372","DOIUrl":"10.1016/j.apradiso.2025.112372","url":null,"abstract":"<div><h3>Background</h3><div>Medical imaging is a major source of ionizing radiation exposure in healthcare. Effective radiation protection relies not only on facility design but also on healthcare staff <strong>knowledge, attitudes, and practices (KAP). Objective</strong>: To evaluate KAP related to radiation protection among staff at two nuclear medicine facilities such as Facility A and Facility B in Addis Ababa, Ethiopia, and assess relationships with occupational exposure and facility design.</div></div><div><h3>Methods</h3><div>A <strong>cross-sectional study</strong> was conducted among 28 personnel using structured questionnaires, checklists, and interviews. KAP scores were calculated, with thresholds for satisfactory performance defined as <strong>≥67 % for knowledge, attitude (corrected for misconceptions), and practice</strong>. Occupational doses were measured and compared with ICRP limits.</div></div><div><h3>Results</h3><div><strong>Eighty-five point seven percent of participants demonstrated satisfactory knowledge, while only 64.3 % had a good attitude after correcting misconceptions, such as the incorrect belief that dosimeters prevent all radiation. Seventy-five percent of personnel followed adequate radiation protection practices. The mean annual occupational dose was 0.33 ± 0.13 mSv, significantly below the ICRP limit of 20 mSv/year, indicating low actual exposure despite some gaps in understanding</strong>. Although education and occupation influenced practice, no statistically significant associations were found with overall knowledge, attitude, and practice (KAP) scores.</div></div><div><h3>Conclusion</h3><div>While personnel show adequate knowledge and practice, critical misconceptions about dosimeter function remain. Continuous training and education are necessary to correct these misconceptions. Occupational exposure levels are low, but improved safety culture and awareness are needed to maintain long-term protection. <strong>Future research should explore correlations between individual KAP scores and dose readings.</strong></div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112372"},"PeriodicalIF":1.8,"publicationDate":"2025-12-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145733561","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}
Low dose induced hyper-radiosensitivity refers to the acquired sensitivity to ionizing radiation due to the exposure to radiation doses <1Gy. Therefore, the aim of the present study was to evaluate whether induction of the hyper-radiosensitivity phenomenon in prostate cancer cells could improve the outcome of 177Lu-iPSMA therapy. Reduction in viability, loss of clonal expansion capacity and decrease of LNCaP prostate cancer cells survival by the promotion of cell apoptosis, is enhanced by gamma irradiation at doses of less than 1 Gy (60Co Gammacell 220 system, 0.24 Gy/min) prior to administration of the targeted radiopharmaceutical. Analysis of survival curves, showed that 0.50 Gy is the predose that improved the TRT therapeutic effect. Pre-irradiation significantly reduced the LNCaP α⁄β ratio from 4.65 to 1.38 in LNCaP cells that received a177Lu-iPSMA absorbed radiation dose to the nucleus between 2 and 10 Gy.
{"title":"Low dose hyper-radiosensitivity as an intervention strategy to enhance 177Lu-iPSMA treatment in LNCaP cells","authors":"Consuelo Letechipia-de León , Erika Patricia Azorín-Vega , Valeria Areli Cabral-Venegas , David Ordaz-Rosado , Fabiola Herrera-García","doi":"10.1016/j.apradiso.2025.112360","DOIUrl":"10.1016/j.apradiso.2025.112360","url":null,"abstract":"<div><div>Low dose induced hyper-radiosensitivity refers to the acquired sensitivity to ionizing radiation due to the exposure to radiation doses <1Gy. Therefore, the aim of the present study was to evaluate whether induction of the hyper-radiosensitivity phenomenon in prostate cancer cells could improve the outcome of <sup>177</sup>Lu-iPSMA therapy. Reduction in viability, loss of clonal expansion capacity and decrease of LNCaP prostate cancer cells survival by the promotion of cell apoptosis, is enhanced by gamma irradiation at doses of less than 1 Gy (<sup>60</sup>Co Gammacell 220 system, 0.24 Gy/min) prior to administration of the targeted radiopharmaceutical. Analysis of survival curves, showed that 0.50 Gy is the predose that improved the TRT therapeutic effect. Pre-irradiation significantly reduced the LNCaP α⁄β ratio from 4.65 to 1.38 in LNCaP cells that received a<sup>177</sup>Lu-iPSMA absorbed radiation dose to the nucleus between 2 and 10 Gy.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112360"},"PeriodicalIF":1.8,"publicationDate":"2025-12-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145733564","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 : 2025-12-05DOI: 10.1016/j.apradiso.2025.112366
E.O. Echeweozo , M.S. Al-Buriahi , Talal M. Althagafi , Jamila S. Alzahrani
Zirconium (Zr) based ceramic glass is a commonly utilized glass ceramic due to its exceptional mechanical and chemical properties. These materials exhibit high durability and resistance to acid attack, making them prospective materials for ionizing radiation protection applications. This study aims to evaluate the neutron and gamma radiation shielding properties of a Zirconium (Zr) based glass ceramics (ASZx) by computing the Linear attenuation coefficient (LAC), Mean free path (MFP), Half-value layer (HVL), Effective atomic number (Zeff), and Fast neutron removal cross-section (FNRCS) using WinXCOM at different photon energies. The samples were formulated using varying molar percentages (mol%) of Aluminum Oxide (Al2O3), Silicon dioxide (SiO2), and Zirconia (ZrO2) to produce Al2O3-SiO2-ZrO2. Results show that ASZ1 displays the highest LAC of 37.71 cm−1 and MAC value of 10.47 cm2/g at 0.015 MeV, trailed by ASZ2 and ASZ3, demonstrating that ceramic glasses with higher Zr have higher attenuation properties at lower energies. The result also showed that ASZ1 exhibited a maximum FNRCS value of 0.1072 cm−1, indicating that a composition of ASZ1 ceramic glass is effective in fast neutron shielding than some traditional neutron shielding materials. This suggests that the ASZx ceramic glass system is a potential alternative to commercially available SCHOTT shielding glasses for some special applications.
{"title":"Computational analysis of neutron and gamma ray shielding efficiency in Al2O3-SiO2-ZrO2 ceramic glass systems for special shielding applications","authors":"E.O. Echeweozo , M.S. Al-Buriahi , Talal M. Althagafi , Jamila S. Alzahrani","doi":"10.1016/j.apradiso.2025.112366","DOIUrl":"10.1016/j.apradiso.2025.112366","url":null,"abstract":"<div><div>Zirconium (Zr) based ceramic glass is a commonly utilized glass ceramic due to its exceptional mechanical and chemical properties. These materials exhibit high durability and resistance to acid attack, making them prospective materials for ionizing radiation protection applications. This study aims to evaluate the neutron and gamma radiation shielding properties of a Zirconium (Zr) based glass ceramics (ASZx) by computing the Linear attenuation coefficient (LAC), Mean free path (MFP), Half-value layer (HVL), Effective atomic number (Z<sub>eff</sub>), and Fast neutron removal cross-section (FNRCS) using WinXCOM at different photon energies. The samples were formulated using varying molar percentages (mol%) of Aluminum Oxide (Al<sub>2</sub>O<sub>3</sub>), Silicon dioxide (SiO<sub>2</sub>), and Zirconia (ZrO<sub>2</sub>) to produce Al<sub>2</sub>O<sub>3</sub>-SiO<sub>2</sub>-ZrO<sub>2</sub>. Results show that ASZ1 displays the highest LAC of 37.71 cm<sup>−1</sup> and MAC value of 10.47 cm<sup>2</sup>/g at 0.015 MeV, trailed by ASZ2 and ASZ3, demonstrating that ceramic glasses with higher Zr have higher attenuation properties at lower energies. The result also showed that ASZ1 exhibited a maximum FNRCS value of 0.1072 cm<sup>−1,</sup> indicating that a composition of ASZ1 ceramic glass is effective in fast neutron shielding than some traditional neutron shielding materials. This suggests that the ASZx ceramic glass system is a potential alternative to commercially available SCHOTT shielding glasses for some special applications.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112366"},"PeriodicalIF":1.8,"publicationDate":"2025-12-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145682641","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 : 2025-12-04DOI: 10.1016/j.apradiso.2025.112370
N. Gutiérrez , A. Coma , A. Tarancón , H. Bagán
PSresins have arisen in the past years as a promising material for the measurement of radioactivity. PSresins are a material composed of a PSm support coated with a selective extractant on its surface, allowing the separation and measurement. However, for some applications, a capacity problem could be presented due to the flat surface of the PSm support. For this reason, the objective of this study has been to prepare a macroporous PSm support that allows the preparation of a PSresin for 99Tc with higher capacity than the current existing PSresin. To achieve this, two porogens, dodecane and heptane, were studied. Both produce pores on the surface with similar diameter, but heptane has the best radiometric characteristics. Several proportions of heptane were studied, observing that an increase in the porogen content increased the surface area and PSm diameter, but with a low effect on the radiometric characteristics. Finally, PSresin for 99Tc were prepared with these supports. The more porous supports could accept a higher quantity of extractant, thereby increasing the capacity of the PSresin, without significant effect on the radiometric characteristics or the sample volume at which the extractant starts leaching.
{"title":"New macroporous support for the preparation of plastic scintillation resins","authors":"N. Gutiérrez , A. Coma , A. Tarancón , H. Bagán","doi":"10.1016/j.apradiso.2025.112370","DOIUrl":"10.1016/j.apradiso.2025.112370","url":null,"abstract":"<div><div>PSresins have arisen in the past years as a promising material for the measurement of radioactivity. PSresins are a material composed of a PSm support coated with a selective extractant on its surface, allowing the separation and measurement. However, for some applications, a capacity problem could be presented due to the flat surface of the PSm support. For this reason, the objective of this study has been to prepare a macroporous PSm support that allows the preparation of a PSresin for <sup>99</sup>Tc with higher capacity than the current existing PSresin. To achieve this, two porogens, dodecane and heptane, were studied. Both produce pores on the surface with similar diameter, but heptane has the best radiometric characteristics. Several proportions of heptane were studied, observing that an increase in the porogen content increased the surface area and PSm diameter, but with a low effect on the radiometric characteristics. Finally, PSresin for <sup>99</sup>Tc were prepared with these supports. The more porous supports could accept a higher quantity of extractant, thereby increasing the capacity of the PSresin, without significant effect on the radiometric characteristics or the sample volume at which the extractant starts leaching.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112370"},"PeriodicalIF":1.8,"publicationDate":"2025-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145682642","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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