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Assessment of cellular dose and damage induced by radon and its progeny using the BEAS-2B cell mesh model
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-02-21 DOI: 10.1016/j.apradiso.2025.111749
Han Gao , Yidi Wang , Jiahao Guo , Huiyuan Xue , Xinjie Wang , Kaijin Yan , Tao Wu , Xiaotong Gao , Haiyang Li , Liang Sun
The decay of radon and its progeny mainly produces α particles and β particles. Due to their short range and high linear energy transfer (LET) of α particles, it is necessary to evaluate the dose deposition at the cellular and subcellular levels so as to better assess their health effects on the human body. Given that the lung is the primary target organ for radon exposure, we utilized human bronchial epithelial cells (BEAS-2B cells) to construct a realistic mesh model. Using Monte Carlo simulation software PHITS, we computed cellular S-values under conditions of radon and progeny irradiation, the deposited does inside cells of nuclide that distribute outside cells has been calculated. These calculations were contrasted with results obtained from traditional geometric models and MIRDcell calculations. To quantify the damage effects caused by radon and its progeny, this study used MCDS to calculate the DNA damage, for various nuclides, Rn-222 produces the highest number of double-strand breaks (DSBs) up to 21.8 Gy-1cell-1, while Tl-210 produces the least DSBs with 8.32 Gy-1cell-1. Additionally, other damage metrics such as single-strand breaks (SSBs), “OTHER”, and “ALL CLUSTERS” were quantified. This research, based on the BEAS-2B cell model, offers more precise information on cellular doses and damage effects of radon and its progeny. It holds significant implications for the future development of radiation protection strategies and applications in radon therapy.
{"title":"Assessment of cellular dose and damage induced by radon and its progeny using the BEAS-2B cell mesh model","authors":"Han Gao ,&nbsp;Yidi Wang ,&nbsp;Jiahao Guo ,&nbsp;Huiyuan Xue ,&nbsp;Xinjie Wang ,&nbsp;Kaijin Yan ,&nbsp;Tao Wu ,&nbsp;Xiaotong Gao ,&nbsp;Haiyang Li ,&nbsp;Liang Sun","doi":"10.1016/j.apradiso.2025.111749","DOIUrl":"10.1016/j.apradiso.2025.111749","url":null,"abstract":"<div><div>The decay of radon and its progeny mainly produces α particles and β particles. Due to their short range and high linear energy transfer (LET) of α particles, it is necessary to evaluate the dose deposition at the cellular and subcellular levels so as to better assess their health effects on the human body. Given that the lung is the primary target organ for radon exposure, we utilized human bronchial epithelial cells (BEAS-2B cells) to construct a realistic mesh model. Using Monte Carlo simulation software PHITS, we computed cellular S-values under conditions of radon and progeny irradiation, the deposited does inside cells of nuclide that distribute outside cells has been calculated. These calculations were contrasted with results obtained from traditional geometric models and MIRDcell calculations. To quantify the damage effects caused by radon and its progeny, this study used MCDS to calculate the DNA damage, for various nuclides, Rn-222 produces the highest number of double-strand breaks (DSBs) up to 21.8 Gy-1cell-1, while Tl-210 produces the least DSBs with 8.32 Gy-1cell-1. Additionally, other damage metrics such as single-strand breaks (SSBs), “OTHER”, and “ALL CLUSTERS” were quantified. This research, based on the BEAS-2B cell model, offers more precise information on cellular doses and damage effects of radon and its progeny. It holds significant implications for the future development of radiation protection strategies and applications in radon therapy.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111749"},"PeriodicalIF":1.6,"publicationDate":"2025-02-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143511325","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}
引用次数: 0
Acceleration of BNCT dose map calculations via convolutional neural networks
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-02-20 DOI: 10.1016/j.apradiso.2025.111718
G. Marzik , M.E. Capoulat , A.J. Kreiner , D.M. Minsky
A carefully made treatment plan is of paramount importance in order to achieve satisfactory results in treatments based on Boron Neutron Capture Therapy. Different source configurations and positions have to be analyzed, and based on the different dose maps that can be computed, an optimal treatment should be chosen. Nowadays the dose maps are computed using slow and computationally intensive Monte Carlo simulations, which hinder the formulation of an optimized treatment plan. This work proposes a machine learning algorithm based on a convolutional neural network that accelerates the convergence of Monte Carlo neutron transport simulations, drastically reducing computation time without loss of accuracy. A dataset of Monte Carlo simulation was made and used for the training of the proposed model. 97% of the voxels of the set of testing simulations had errors lower than 5% when processed by the neural network, and inference times were reduced by three orders of magnitude. In the future, this tool could allow a real optimization of treatment plans.
{"title":"Acceleration of BNCT dose map calculations via convolutional neural networks","authors":"G. Marzik ,&nbsp;M.E. Capoulat ,&nbsp;A.J. Kreiner ,&nbsp;D.M. Minsky","doi":"10.1016/j.apradiso.2025.111718","DOIUrl":"10.1016/j.apradiso.2025.111718","url":null,"abstract":"<div><div>A carefully made treatment plan is of paramount importance in order to achieve satisfactory results in treatments based on Boron Neutron Capture Therapy. Different source configurations and positions have to be analyzed, and based on the different dose maps that can be computed, an optimal treatment should be chosen. Nowadays the dose maps are computed using slow and computationally intensive Monte Carlo simulations, which hinder the formulation of an optimized treatment plan. This work proposes a machine learning algorithm based on a convolutional neural network that accelerates the convergence of Monte Carlo neutron transport simulations, drastically reducing computation time without loss of accuracy. A dataset of Monte Carlo simulation was made and used for the training of the proposed model. 97% of the voxels of the set of testing simulations had errors lower than 5% when processed by the neural network, and inference times were reduced by three orders of magnitude. In the future, this tool could allow a real optimization of treatment plans.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111718"},"PeriodicalIF":1.6,"publicationDate":"2025-02-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143479019","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}
引用次数: 0
Radiation attenuation parameters and intrinsic efficiency of a few semiconductor crystals for radiation detection applications
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-02-20 DOI: 10.1016/j.apradiso.2025.111747
P. Vipin Kumar, Anagha P. Vincent, Srilakshmi Prabhu, S.G. Bubbly, S.B. Gudennavar
This study investigates the effectiveness of nine inorganic semiconductor crystals − LiGaSe2, LiInSe2, CsHgInS3, SnS, GaTe, BiI3, Sb2Te3, Tl4CdI6, and TlBr − for radiation detection applications based on photon and charged particle (electrons, protons, and heavy ions) interaction parameters. Mass attenuation coefficient (μ/ρ), half value layer (HVL), relaxation length (λ), effective atomic number (Zeff), electron density (Neff), equivalent atomic number (Zeq), and exposure buildup factor (EBF) were computed using PAGEX software. These results, along with their intrinsic efficiencies calculated, were compared with that of standard materials (NaI(Tl), CdZnTe, and CdTe). The μ/ρ values of the studied semiconducting materials are ranked in the decreasing order as: TlBr, Tl4CdI6, BiI3, CsHgInS3, Sb2Te3, GaTe, SnS, LiInSe2, and LiGaSe2. TlBr, Tl4CdI6, BiI3, and Sb2Te3 show superior photon detection capabilities compared to the reference materials. TlBr and Tl4CdI6 have the highest intrinsic efficiency across nearly all energy regions, while LiGaSe2 has the lowest. Interaction parameters like range and Zeff for charged particles were also computed using standard databases, with SnS and Sb2Te3 showing the least range for all the charged particles studied throughout the entire energy region. The study indicates that TlBr and Tl4CdI6 have strong potential for developing next-generation radiation detectors with enhanced sensitivity, addressing needs in healthcare and national security.
{"title":"Radiation attenuation parameters and intrinsic efficiency of a few semiconductor crystals for radiation detection applications","authors":"P. Vipin Kumar,&nbsp;Anagha P. Vincent,&nbsp;Srilakshmi Prabhu,&nbsp;S.G. Bubbly,&nbsp;S.B. Gudennavar","doi":"10.1016/j.apradiso.2025.111747","DOIUrl":"10.1016/j.apradiso.2025.111747","url":null,"abstract":"<div><div>This study investigates the effectiveness of nine inorganic semiconductor crystals − LiGaSe<sub>2</sub>, LiInSe<sub>2</sub>, CsHgInS<sub>3</sub>, SnS, GaTe, BiI<sub>3</sub>, Sb<sub>2</sub>Te<sub>3</sub>, Tl<sub>4</sub>CdI<sub>6</sub>, and TlBr − for radiation detection applications based on photon and charged particle (electrons, protons, and heavy ions) interaction parameters. Mass attenuation coefficient (μ/ρ), half value layer (HVL), relaxation length (λ), effective atomic number (Z<sub>eff</sub>), electron density (N<sub>eff</sub>), equivalent atomic number (Z<sub>eq</sub>), and exposure buildup factor (EBF) were computed using PAGEX software. These results, along with their intrinsic efficiencies calculated, were compared with that of standard materials (NaI(Tl), CdZnTe, and CdTe). The μ/ρ values of the studied semiconducting materials are ranked in the decreasing order as: TlBr, Tl<sub>4</sub>CdI<sub>6</sub>, BiI<sub>3</sub>, CsHgInS<sub>3</sub>, Sb<sub>2</sub>Te<sub>3</sub>, GaTe, SnS, LiInSe<sub>2</sub>, and LiGaSe<sub>2</sub>. TlBr, Tl<sub>4</sub>CdI<sub>6</sub>, BiI<sub>3</sub>, and Sb<sub>2</sub>Te<sub>3</sub> show superior photon detection capabilities compared to the reference materials. TlBr and Tl<sub>4</sub>CdI<sub>6</sub> have the highest intrinsic efficiency across nearly all energy regions, while LiGaSe<sub>2</sub> has the lowest. Interaction parameters like range and Z<sub>eff</sub> for charged particles were also computed using standard databases, with SnS and Sb<sub>2</sub>Te<sub>3</sub> showing the least range for all the charged particles studied throughout the entire energy region. The study indicates that TlBr and Tl<sub>4</sub>CdI<sub>6</sub> have strong potential for developing next-generation radiation detectors with enhanced sensitivity, addressing needs in healthcare and national security.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111747"},"PeriodicalIF":1.6,"publicationDate":"2025-02-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143563309","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}
引用次数: 0
Simulation and verification of a slim X-ray density logging tool
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-02-19 DOI: 10.1016/j.apradiso.2025.111741
Jilin Fan, Jiaqi XiangYang, Qiong Zhang
With advancements in oil and gas exploration, the design and measurement methods of X-ray density logging tools have gained significant attention as a new generation of controllable sources. Using an existing ultra-slim gamma tool as an example, this work shows how the tool could be re-designed by replacing the gamma source with an X-ray source. The key aspects of this study include: 1) Simulating the production of X-ray with different energies; 2) Studying the optimum spacing of X-ray logging tool by considering the factors of detection efficiency, density measurement sensitivity, and depth of investigation; 3) Performing X-ray density measurements using multivariable forward and inversion methods and comparing the results with gamma density logging. The findings reveal that by adjusting the spacing of near and far detectors to 110 mm and 290 mm respectively, the X-ray logging tool achieves performance comparable to or even surpassing it of the gamma tool. In comparison to gamma logging, X-ray logging demonstrates superior formation sensitivity, vertical resolution, and formation density measurement accuracy. Notably, in heavy mudcake condition, the X-ray logging tool enhances the Pe measurement accuracy by 47%. These investigations serve as valuable insights for the forward design of X-ray logging tools and formation density measurements.
{"title":"Simulation and verification of a slim X-ray density logging tool","authors":"Jilin Fan,&nbsp;Jiaqi XiangYang,&nbsp;Qiong Zhang","doi":"10.1016/j.apradiso.2025.111741","DOIUrl":"10.1016/j.apradiso.2025.111741","url":null,"abstract":"<div><div>With advancements in oil and gas exploration, the design and measurement methods of X-ray density logging tools have gained significant attention as a new generation of controllable sources. Using an existing ultra-slim gamma tool as an example, this work shows how the tool could be re-designed by replacing the gamma source with an X-ray source. The key aspects of this study include: 1) Simulating the production of X-ray with different energies; 2) Studying the optimum spacing of X-ray logging tool by considering the factors of detection efficiency, density measurement sensitivity, and depth of investigation; 3) Performing X-ray density measurements using multivariable forward and inversion methods and comparing the results with gamma density logging. The findings reveal that by adjusting the spacing of near and far detectors to 110 mm and 290 mm respectively, the X-ray logging tool achieves performance comparable to or even surpassing it of the gamma tool. In comparison to gamma logging, X-ray logging demonstrates superior formation sensitivity, vertical resolution, and formation density measurement accuracy. Notably, in heavy mudcake condition, the X-ray logging tool enhances the Pe measurement accuracy by 47%. These investigations serve as valuable insights for the forward design of X-ray logging tools and formation density measurements.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111741"},"PeriodicalIF":1.6,"publicationDate":"2025-02-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143474662","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}
引用次数: 0
Simulation of diffusion and decay of radon/thoron exhaled from a wall and its newly created progeny. Response of a bare LR-115 detector placed on the wall
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-02-19 DOI: 10.1016/j.apradiso.2025.111743
Daniel Francisco Palacios Fernández , Patrizia Edel Pereyra Anaya , Laszlo Sajo-Bohus
Monte Carlo techniques were used to simulate the air diffusion of exhaled radon/thoron atoms from a wall, the formation and decay of different radioactive species during transport, and the response of a bare LR-115 detector placed on the exhaling surface. The spatial distributions of radionuclide decays and the detector's partial sensitivities to radon/thoron and their progeny were determined. The simulation results were numerically validated through comparisons with published theoretical and experimental data. From the simulated experiments, the contributions of different species to the total track density and what the detector might measure in the studied configuration and assumed parameters were inferred. It was shown that near the wall, where the effective volumes of all species are located, the number of radon atoms was approximately constant, while that of thoron decreased to about 30% relative to the number of exhaled atoms, and the equilibrium factors of both gases were very low. A negligible contribution of 220Rn and 216Po to the track density is expected if the distance between detector's edges and support exceeds 5–6 times the thoron characteristic diffusion length. For similar detector and support sizes, these atoms can significantly contribute to the track density if thoron exhalation rate from wall is high. The advantages and limitations of the detector exposure method for estimating indoor radon concentrations are analyzed. Finally, a simple method is suggested for more accurate radon measurements using the bare LR-115 detector placed on a wall.
{"title":"Simulation of diffusion and decay of radon/thoron exhaled from a wall and its newly created progeny. Response of a bare LR-115 detector placed on the wall","authors":"Daniel Francisco Palacios Fernández ,&nbsp;Patrizia Edel Pereyra Anaya ,&nbsp;Laszlo Sajo-Bohus","doi":"10.1016/j.apradiso.2025.111743","DOIUrl":"10.1016/j.apradiso.2025.111743","url":null,"abstract":"<div><div>Monte Carlo techniques were used to simulate the air diffusion of exhaled radon/thoron atoms from a wall, the formation and decay of different radioactive species during transport, and the response of a bare LR-115 detector placed on the exhaling surface. The spatial distributions of radionuclide decays and the detector's partial sensitivities to radon/thoron and their progeny were determined. The simulation results were numerically validated through comparisons with published theoretical and experimental data. From the simulated experiments, the contributions of different species to the total track density and what the detector might measure in the studied configuration and assumed parameters were inferred. It was shown that near the wall, where the effective volumes of all species are located, the number of radon atoms was approximately constant, while that of thoron decreased to about 30% relative to the number of exhaled atoms, and the equilibrium factors of both gases were very low. A negligible contribution of <sup>220</sup>Rn and <sup>216</sup>Po to the track density is expected if the distance between detector's edges and support exceeds 5–6 times the thoron characteristic diffusion length. For similar detector and support sizes, these atoms can significantly contribute to the track density if thoron exhalation rate from wall is high. The advantages and limitations of the detector exposure method for estimating indoor radon concentrations are analyzed. Finally, a simple method is suggested for more accurate radon measurements using the bare LR-115 detector placed on a wall.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111743"},"PeriodicalIF":1.6,"publicationDate":"2025-02-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143479020","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}
引用次数: 0
From the atomic nucleus to cancer cure: The marvel of BNCT a nuclear physicist views. Achievements and outstanding problems
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-02-18 DOI: 10.1016/j.apradiso.2025.111725
Andrés J. Kreiner
The interdisciplinary character of the BNCT endeavour is stressed ranging from nuclear physics to most of the natural and exact sciences.
Radiobiology studies, carried out with accelerated proton, alpha and Li beams, are used to isolate the relative biological effectiveness of “pure” high LET radiation. Based on the survival curve results, we discuss the question of the use of fixed RBE factors to convert physical doses into equivalent or isoeffective gamma doses. Furthermore, the necessity of converting physical doses into equivalent or isoeffective gamma doses is questioned. Tumor Control Probabilities are discussed and used as a tool to optimize Beam Shaping Assemblies.
Boron microdistribution studies are mentioned and the lack of a sufficiently complete method to cover the whole tumor, given the heterogeneity in 3D, is pointed out.
The development of Prompt Gamma Single Photon Emission Computed Tomography, PG-SPECT, systems especially tailored for BNCT are discussed stressing them as a powerful way of determining in real time the macroscopic average boron dose delivered to the patient.
Studies of deuteron-induced neutron-producing are reviewed and the development of electrostatic quadrupole technology for BNCT is highlighted.
{"title":"From the atomic nucleus to cancer cure: The marvel of BNCT a nuclear physicist views. Achievements and outstanding problems","authors":"Andrés J. Kreiner","doi":"10.1016/j.apradiso.2025.111725","DOIUrl":"10.1016/j.apradiso.2025.111725","url":null,"abstract":"<div><div>The interdisciplinary character of the BNCT endeavour is stressed ranging from nuclear physics to most of the natural and exact sciences.</div><div>Radiobiology studies, carried out with accelerated proton, alpha and Li beams, are used to isolate the relative biological effectiveness of “pure” high LET radiation. Based on the survival curve results, we discuss the question of the use of fixed RBE factors to convert physical doses into equivalent or isoeffective gamma doses. Furthermore, the necessity of converting physical doses into equivalent or isoeffective gamma doses is questioned. Tumor Control Probabilities are discussed and used as a tool to optimize Beam Shaping Assemblies.</div><div>Boron microdistribution studies are mentioned and the lack of a sufficiently complete method to cover the whole tumor, given the heterogeneity in 3D, is pointed out.</div><div>The development of Prompt Gamma Single Photon Emission Computed Tomography, PG-SPECT, systems especially tailored for BNCT are discussed stressing them as a powerful way of determining in real time the macroscopic average boron dose delivered to the patient.</div><div>Studies of deuteron-induced neutron-producing are reviewed and the development of electrostatic quadrupole technology for BNCT is highlighted.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111725"},"PeriodicalIF":1.6,"publicationDate":"2025-02-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143509480","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}
引用次数: 0
The impact of TeO2 content on radiation shielding properties for zinc-tellurite borosilicate glasses TeO2 含量对锌碲硼硅玻璃辐射屏蔽性能的影响
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-02-18 DOI: 10.1016/j.apradiso.2025.111742
A.S. Mostafa , M.M. Kassab , M.M. Radwan , Ahmed M. Al Kaisy , A. Abdel-Latif M
A novel Zinc-Tellurite borosilicate (ZTBS) glass system was successfully synthesized via the melt quench process. Its chemical composition is represented by the formula (44SiO2-25B2O3-18Na2O-6CaO-1ZrO2-(6-x)ZnO-xTeO2), and its weight fraction (x = 0, 2, 4, 6 wt%). The shielding properties, there is perfect agreement between the results of the theoretical calculation of the mass attenuation coefficient using the Phy-X/PSD and the compatible values derived from the WinXCom databases. Further, several photon shielding parameters were computed in the 15 keV–15 MeV energy range, including the mass attenuation coefficient (MAC), half value layer (HVL), mean free path (MFP), exposure buildup factor (EBF), and effective atomic number (Zeff). The preferred sample for gamma ray shielding is the sample with the highest TeO2 concentration (ZTBS3), according to the results. ZTBS3 glass samples have greater MAC and HVL values than other published borosilicate glasses at 662.61 k eV photon energy which reaches 0.07626 cm−2/g and 3.429 cm respectively. Also, LAC values is higher in the sample with the largest concentration of TeO2. Furthermore, the computed HVL and MFP were lower than those of regular concrete. The shielding results indicate that the newly developed transparent ZTBS glasses compositions that are lightweight and have good shielding properties that may be suitable in shielding applications. Depending on the application, the ratio of TeO2 additive should be balanced between improved shielding and glass stability features.
{"title":"The impact of TeO2 content on radiation shielding properties for zinc-tellurite borosilicate glasses","authors":"A.S. Mostafa ,&nbsp;M.M. Kassab ,&nbsp;M.M. Radwan ,&nbsp;Ahmed M. Al Kaisy ,&nbsp;A. Abdel-Latif M","doi":"10.1016/j.apradiso.2025.111742","DOIUrl":"10.1016/j.apradiso.2025.111742","url":null,"abstract":"<div><div>A novel Zinc-Tellurite borosilicate (ZTBS) glass system was successfully synthesized via the melt quench process. Its chemical composition is represented by the formula (44SiO<sub>2</sub>-25B<sub>2</sub>O<sub>3</sub>-18Na<sub>2</sub>O-6CaO-1ZrO<sub>2</sub>-(6-x)ZnO-xTeO<sub>2</sub>), and its weight fraction (x = 0, 2, 4, 6 wt%). The shielding properties, there is perfect agreement between the results of the theoretical calculation of the mass attenuation coefficient using the Phy-X/PSD and the compatible values derived from the WinXCom databases. Further, several photon shielding parameters were computed in the 15 keV–15 MeV energy range, including the mass attenuation coefficient (MAC), half value layer (HVL), mean free path (MFP), exposure buildup factor (EBF), and effective atomic number (Z<sub>eff</sub>). The preferred sample for gamma ray shielding is the sample with the highest TeO<sub>2</sub> concentration (ZTBS3), according to the results. ZTBS3 glass samples have greater MAC and HVL values than other published borosilicate glasses at 662.61 k eV photon energy which reaches 0.07626 cm<sup>−2</sup>/g and 3.429 cm respectively. Also, LAC values is higher in the sample with the largest concentration of TeO<sub>2</sub>. Furthermore, the computed HVL and MFP were lower than those of regular concrete. The shielding results indicate that the newly developed transparent ZTBS glasses compositions that are lightweight and have good shielding properties that may be suitable in shielding applications. Depending on the application, the ratio of TeO<sub>2</sub> additive should be balanced between improved shielding and glass stability features.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111742"},"PeriodicalIF":1.6,"publicationDate":"2025-02-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143479018","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}
引用次数: 0
Study of the reduction in the time of counting in spectrometric analysis using HPGe detector for samples of fresh organic foods
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-02-18 DOI: 10.1016/j.apradiso.2025.111744
Nadia Rodrigues dos Santos , Alessandro Mariano Domingues , Izabella Soares de Souza , Carlos Omar Pastrana Orejuela , Ademir Xavier da Silva , Edmilson Monteiro de Souza , Inayá Corrêa Barbosa Lima
The quantification of natural radionuclides within environmental matrices is commonly executed via gamma spectrometry, employing HPGe detector. Variability in counting times is reported in the literature, often predicated on empirical knowledge. This study aims to estimate a reduction in counting time in the process of analyzing activity concentration of 40K radionuclide, based on reducing the percentage variation of their uncertainties, in some fresh and frozen organic vegetables, grown in an environmental conservation unit. For each sample, 10 count measurements were taken at regular intervals of 3600 s over a period of 36,000 s using the HPGe detector and the Genie 2000 data acquisition software. The background spectrum was obtained at the same time intervals and with the same sample geometry. Efficiency curves and self-attenuation corrections were performed using the LabSOCS software. Considering the counting times 25,200 s and 36,000 s, the determined 40K activity concentration (Bq.kg−1) for lady's finger banana, cabbage and carrot were (107 ± 16.49; 109 ± 16.35), (79 ± 12.77; 81 ± 12.62) and (100 ± 15.44; 102 ± 15.36), respectively. The activity concentrate uncertainty starts to vary slightly and began to stabilize from 25,200s onwards. The results indicate that considering the employed methodology, extending the counting time for fresh and frozen organic foods would not yield a significant advantage over reducing the detector operation time.
{"title":"Study of the reduction in the time of counting in spectrometric analysis using HPGe detector for samples of fresh organic foods","authors":"Nadia Rodrigues dos Santos ,&nbsp;Alessandro Mariano Domingues ,&nbsp;Izabella Soares de Souza ,&nbsp;Carlos Omar Pastrana Orejuela ,&nbsp;Ademir Xavier da Silva ,&nbsp;Edmilson Monteiro de Souza ,&nbsp;Inayá Corrêa Barbosa Lima","doi":"10.1016/j.apradiso.2025.111744","DOIUrl":"10.1016/j.apradiso.2025.111744","url":null,"abstract":"<div><div>The quantification of natural radionuclides within environmental matrices is commonly executed via gamma spectrometry, employing HPGe detector. Variability in counting times is reported in the literature, often predicated on empirical knowledge. This study aims to estimate a reduction in counting time in the process of analyzing activity concentration of <sup>40</sup>K radionuclide, based on reducing the percentage variation of their uncertainties, in some fresh and frozen organic vegetables, grown in an environmental conservation unit. For each sample, 10 count measurements were taken at regular intervals of 3600 s over a period of 36,000 s using the HPGe detector and the Genie 2000 data acquisition software. The background spectrum was obtained at the same time intervals and with the same sample geometry. Efficiency curves and self-attenuation corrections were performed using the LabSOCS software. Considering the counting times 25,200 s and 36,000 s, the determined <sup>40</sup>K activity concentration (Bq.kg<sup>−1</sup>) for lady's finger banana, cabbage and carrot were (107 ± 16.49; 109 ± 16.35), (79 ± 12.77; 81 ± 12.62) and (100 ± 15.44; 102 ± 15.36), respectively. The activity concentrate uncertainty starts to vary slightly and began to stabilize from 25,200s onwards. The results indicate that considering the employed methodology, extending the counting time for fresh and frozen organic foods would not yield a significant advantage over reducing the detector operation time.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111744"},"PeriodicalIF":1.6,"publicationDate":"2025-02-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143471353","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}
引用次数: 0
Assessment of organ dose for adult undergoing CT examinations: Comparison of three software applications using Monte Carlo simulation
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-02-17 DOI: 10.1016/j.apradiso.2025.111740
Maria Hakme , Ziad Francis , Chadia Rizk , Georges Fares
Understanding organ dose during CT scans is crucial due to cancer risks from low-level radiation exposure. This study aims to analyze and compare different methods for estimating CT organ doses in adult male and female patients, assessing the compatibility of NCICT with standard phantoms and NCICT with body size adjustment with GEANT4 simulations. It also evaluates the impact of different CT manufacturers on organ dose calculations. Previous research used various phantoms to represent organ doses across age groups. This study utilizes DICOM images from real adult patients undergoing CT scans to evaluate organ dose using the GEANT4 simulation toolkit. A retrospective analysis of 240 CT scans (head, chest, and abdomen-pelvis) compared GEANT4 dose estimates to the software tool NCICT. Data from Siemens and Philips CT scanners were included. Organ doses for 34 organs were calculated using Siemens patient DICOM data, while Philips estimates made using only NCICT with body size adjustment. Statistical analysis assessed differences in organ doses by gender and scanner type. Organ doses for the brain, spinal cord, and liver were higher in females (48.1, 4.9, and 6.7 mGy) compared to males (42.5, 4.4, and 6.3 mGy). NCICT with body size adjustment estimates were more consistent with GEANT4 (differences up to 18%) compared to NCICT with standard phantoms (differences up to 46%). Notable variations were found between Siemens and Philips scanners, despite identical detector rows. Accurate models and scanner-specific differences are critical for reliable radiation dose assessments, emphasizing the need for tailored dosimetry to enhance patient safety.
{"title":"Assessment of organ dose for adult undergoing CT examinations: Comparison of three software applications using Monte Carlo simulation","authors":"Maria Hakme ,&nbsp;Ziad Francis ,&nbsp;Chadia Rizk ,&nbsp;Georges Fares","doi":"10.1016/j.apradiso.2025.111740","DOIUrl":"10.1016/j.apradiso.2025.111740","url":null,"abstract":"<div><div>Understanding organ dose during CT scans is crucial due to cancer risks from low-level radiation exposure. This study aims to analyze and compare different methods for estimating CT organ doses in adult male and female patients, assessing the compatibility of NCICT with standard phantoms and NCICT with body size adjustment with GEANT4 simulations. It also evaluates the impact of different CT manufacturers on organ dose calculations. Previous research used various phantoms to represent organ doses across age groups. This study utilizes DICOM images from real adult patients undergoing CT scans to evaluate organ dose using the GEANT4 simulation toolkit. A retrospective analysis of 240 CT scans (head, chest, and abdomen-pelvis) compared GEANT4 dose estimates to the software tool NCICT. Data from Siemens and Philips CT scanners were included. Organ doses for 34 organs were calculated using Siemens patient DICOM data, while Philips estimates made using only NCICT with body size adjustment. Statistical analysis assessed differences in organ doses by gender and scanner type. Organ doses for the brain, spinal cord, and liver were higher in females (48.1, 4.9, and 6.7 mGy) compared to males (42.5, 4.4, and 6.3 mGy). NCICT with body size adjustment estimates were more consistent with GEANT4 (differences up to 18%) compared to NCICT with standard phantoms (differences up to 46%). Notable variations were found between Siemens and Philips scanners, despite identical detector rows. Accurate models and scanner-specific differences are critical for reliable radiation dose assessments, emphasizing the need for tailored dosimetry to enhance patient safety.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111740"},"PeriodicalIF":1.6,"publicationDate":"2025-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143474664","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}
引用次数: 0
Composite detectors as a beneficial tool for dose measurements of secondary radiation in boron neutron capture therapy
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2025-02-15 DOI: 10.1016/j.apradiso.2025.111726
V. Gorbenko , T. Zorenko , S. Witkiewicz-Łukaszek , B. Sobiech , P. Bilski , M. Gryziński , J. Winiecki , Yu. Zorenko
A concept for studying the effects of secondary radiation in boron neutron capture therapy based on the application of multilayer composite scintillators was proposed in this work. Such composite scintillators can be used for simultaneous measurement of the dose of various types of ionizing radiation, including 7Li ions, α-particles and γ-rays. For this purpose, three types of composite detectors based on the single crystalline films and single crystals of Y3Al5O12 and Lu3Al5O12 garnets, doped with Ce3+, Pr3+ and Sc3+ ions, were produced using the liquid phase epitaxy growth method. The scintillation reader for in-situ dose measurement of different radiation components at BNCT was constructed based on the developed types of composite detectors. The possibility of recording various radiation components was demonstrated using: 1) the differences in the pulse height spectra and scintillation decay kinetics of various parts of composite detectors under excitation by α-particles of 239Pu source; 2) the difference in the radioluminescence spectra of films and crystal scintillators in composite detectors under excitation by γ-rays of 192Ir (392 keV) source. The obtained results were discussed for choice of the best registration methods and types of composite detectors for direct dose measurements of secondary radiation under excitation with thermal neutrons.
{"title":"Composite detectors as a beneficial tool for dose measurements of secondary radiation in boron neutron capture therapy","authors":"V. Gorbenko ,&nbsp;T. Zorenko ,&nbsp;S. Witkiewicz-Łukaszek ,&nbsp;B. Sobiech ,&nbsp;P. Bilski ,&nbsp;M. Gryziński ,&nbsp;J. Winiecki ,&nbsp;Yu. Zorenko","doi":"10.1016/j.apradiso.2025.111726","DOIUrl":"10.1016/j.apradiso.2025.111726","url":null,"abstract":"<div><div>A concept for studying the effects of secondary radiation in boron neutron capture therapy based on the application of multilayer composite scintillators was proposed in this work. Such composite scintillators can be used for simultaneous measurement of the dose of various types of ionizing radiation, including <sup>7</sup>Li ions, α-particles and γ-rays. For this purpose, three types of composite detectors based on the single crystalline films and single crystals of Y<sub>3</sub>Al<sub>5</sub>O<sub>12</sub> and Lu<sub>3</sub>Al<sub>5</sub>O<sub>12</sub> garnets, doped with Ce<sup>3+</sup>, Pr<sup>3+</sup> and Sc<sup>3+</sup> ions, were produced using the liquid phase epitaxy growth method. The scintillation reader for in-situ dose measurement of different radiation components at BNCT was constructed based on the developed types of composite detectors. The possibility of recording various radiation components was demonstrated using: 1) the differences in the pulse height spectra and scintillation decay kinetics of various parts of composite detectors under excitation by α-particles of <sup>239</sup>Pu source; 2) the difference in the radioluminescence spectra of films and crystal scintillators in composite detectors under excitation by γ-rays of <sup>192</sup>Ir (392 keV) source. The obtained results were discussed for choice of the best registration methods and types of composite detectors for direct dose measurements of secondary radiation under excitation with thermal neutrons.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111726"},"PeriodicalIF":1.6,"publicationDate":"2025-02-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143488273","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}
引用次数: 0
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Applied Radiation and Isotopes
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