Applied Radiation and Isotopes最新文献

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Investigation and analysis of the proton-induced reactions on natCu, 65Cu, and 63Cu to produce 62, 63, 65Zn radioisotopes for medical applications

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-03-06 DOI: 10.1016/j.apradiso.2025.111765

Bassam T. Al-Azraq , Noor Ali Hameed

The phenomenological and microscopic level density models were utilized within the TALYS 2.0 software to simulate the cross-sections of proton-induced reactions on both natural and enriched copper. This process resulted in the production of the zinc radioisotopes ⁶²Zn, ⁶³Zn, and ⁶⁵Zn, which hold significance in diagnostic and therapeutic medicine. We assessed the uncertainty values for all computed cross sections by contrasting them with experimental data taken from the EXFOR database. This was undertaken to deliver a thorough and precise account of the predictions across various incident energy, grounded in the relevant uncertainty values associated with each energy value. We calculated the average uncertainty through the relative variance technique to identify the theoretical model that aligns most closely with the experimental data. The simulations demonstrated high accuracy when employing level density models, particularly the Skyrme-Hartree-Fock-Bogolyubov-Goriely's tables (SHFB) model, which exhibited excellent relative variance values for the majority of the reactions analyzed. Furthermore, specific energy values linked to significant uncertainty were recognized, indicating the necessity to steer clear of these energies in upcoming investigations aimed at producing ^62,63,65Zn radioisotopes. The theoretical yield was determined by utilizing the cross-section results derived from the most accurate model for each reaction, followed by a comparison with the experimental values. The majority of the chosen experimental yield values demonstrated strong consistency. The findings suggest that the yield for proton-induced reactions on enriched copper exceeded that of natural copper. Furthermore, the generation of zinc isotopes does not necessitate elevated incident energy, rendering these reactions particularly appropriate for application with small medical cyclotrons.

{"title":"Investigation and analysis of the proton-induced reactions on natCu, 65Cu, and 63Cu to produce 62, 63, 65Zn radioisotopes for medical applications","authors":"Bassam T. Al-Azraq , Noor Ali Hameed","doi":"10.1016/j.apradiso.2025.111765","DOIUrl":"10.1016/j.apradiso.2025.111765","url":null,"abstract":"<div><div>The phenomenological and microscopic level density models were utilized within the TALYS 2.0 software to simulate the cross-sections of proton-induced reactions on both natural and enriched copper. This process resulted in the production of the zinc radioisotopes <sup>62</sup>Zn, <sup>63</sup>Zn, and <sup>65</sup>Zn, which hold significance in diagnostic and therapeutic medicine. We assessed the uncertainty values for all computed cross sections by contrasting them with experimental data taken from the EXFOR database. This was undertaken to deliver a thorough and precise account of the predictions across various incident energy, grounded in the relevant uncertainty values associated with each energy value. We calculated the average uncertainty through the relative variance technique to identify the theoretical model that aligns most closely with the experimental data. The simulations demonstrated high accuracy when employing level density models, particularly the Skyrme-Hartree-Fock-Bogolyubov-Goriely's tables (SHFB) model, which exhibited excellent relative variance values for the majority of the reactions analyzed. Furthermore, specific energy values linked to significant uncertainty were recognized, indicating the necessity to steer clear of these energies in upcoming investigations aimed at producing <sup>62,63,65</sup>Zn radioisotopes. The theoretical yield was determined by utilizing the cross-section results derived from the most accurate model for each reaction, followed by a comparison with the experimental values. The majority of the chosen experimental yield values demonstrated strong consistency. The findings suggest that the yield for proton-induced reactions on enriched copper exceeded that of natural copper. Furthermore, the generation of zinc isotopes does not necessitate elevated incident energy, rendering these reactions particularly appropriate for application with small medical cyclotrons.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111765"},"PeriodicalIF":1.6,"publicationDate":"2025-03-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143593091","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

Analysis of cement raw materials radioactivity in Chongqing

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-03-05 DOI: 10.1016/j.apradiso.2025.111756

Feng Wang , Shang Geng , Chuncen Wu , Hengyan Du , Xiuqin Zhang , Yifan Song , Yang Chen , Mingxiao Wang , Guoqiang Wang , Tianya Huang , Xue Zhao , Fei Li , Guang Li

Under the guidance of national energy-saving and environmental protection policies, the addition of high-radioactivity waste materials to cement may lead to the accumulation of various radioactive elements, potentially harming human health if not properly controlled. This study selected three representative cement production companies in Chongqing for sampling based on their production line processes. The activities of the radionuclides ²²⁶Ra, ²³²Th, and ⁴⁰K in raw materials, fuels, additives, and final products were measured using a low-background high-purity germanium spectrometer. Additionally, the internal and external exposure indices, radium equivalent activity, and annual effective dose were calculated. A curve illustrating the changes in radioactivity was put forward, and the variations in radioactivity during the process from raw materials to final products were analyzed. The main reasons for the changes in radioactivity during cement production were found to be the proportion of raw materials, the addition of high-radioactivity additives, and the accumulation from kiln calcination processes. Based on these findings, recommendations for controlling radioactivity during cement production were provided.

{"title":"Analysis of cement raw materials radioactivity in Chongqing","authors":"Feng Wang , Shang Geng , Chuncen Wu , Hengyan Du , Xiuqin Zhang , Yifan Song , Yang Chen , Mingxiao Wang , Guoqiang Wang , Tianya Huang , Xue Zhao , Fei Li , Guang Li","doi":"10.1016/j.apradiso.2025.111756","DOIUrl":"10.1016/j.apradiso.2025.111756","url":null,"abstract":"<div><div>Under the guidance of national energy-saving and environmental protection policies, the addition of high-radioactivity waste materials to cement may lead to the accumulation of various radioactive elements, potentially harming human health if not properly controlled. This study selected three representative cement production companies in Chongqing for sampling based on their production line processes. The activities of the radionuclides <sup>226</sup>Ra, <sup>232</sup>Th, and <sup>40</sup>K in raw materials, fuels, additives, and final products were measured using a low-background high-purity germanium spectrometer. Additionally, the internal and external exposure indices, radium equivalent activity, and annual effective dose were calculated. A curve illustrating the changes in radioactivity was put forward, and the variations in radioactivity during the process from raw materials to final products were analyzed. The main reasons for the changes in radioactivity during cement production were found to be the proportion of raw materials, the addition of high-radioactivity additives, and the accumulation from kiln calcination processes. Based on these findings, recommendations for controlling radioactivity during cement production were provided.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111756"},"PeriodicalIF":1.6,"publicationDate":"2025-03-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143577280","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

Investigating solid-state reactions in UAl2-Al dispersions for Mo-99 target fabrication

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-03-03 DOI: 10.1016/j.apradiso.2025.111763

Thomaz Augusto Guisard Restivo , Giovanni de Lima Cabral Conturbia , Elita Fontenele Urano de Carvalho , Michelangelo Durazzo

Molybdenum-99 (Mo-99), the parent isotope of the widely used medical radioisotope technetium-99m (Tc-99m), is primarily produced via neutron irradiation of uranium-containing targets in research reactors. UAl₂-Al dispersions, with UAl₂ particles embedded in an aluminum matrix, are commonly employed for target fabrication. This study employs a new method for investigating the solid-state reactions between UAl₂ and the Al matrix during target fabrication using stepwise isothermal dilatometry (SID). The study focuses on the formation of UAl₃ and UAl₄, which are less dense than UAl₂ and result in material expansion detected by the linear displacement, which relates to reaction conversion. By analyzing the linear expansion data from 560 °C to 630 °C, SID determines apparent activation energies and identifies the D2 diffusion rate model as the best fit, indicating a fast reaction rate along the UAl₂/Al interfaces and highlighting the crucial role of interface diffusion in the process. This information is crucial for optimizing target fabrication and controlling the final composition of Mo-99 targets.

{"title":"Investigating solid-state reactions in UAl2-Al dispersions for Mo-99 target fabrication","authors":"Thomaz Augusto Guisard Restivo , Giovanni de Lima Cabral Conturbia , Elita Fontenele Urano de Carvalho , Michelangelo Durazzo","doi":"10.1016/j.apradiso.2025.111763","DOIUrl":"10.1016/j.apradiso.2025.111763","url":null,"abstract":"<div><div>Molybdenum-99 (Mo-99), the parent isotope of the widely used medical radioisotope technetium-99m (Tc-99m), is primarily produced via neutron irradiation of uranium-containing targets in research reactors. UAl<sub>2</sub>-Al dispersions, with UAl<sub>2</sub> particles embedded in an aluminum matrix, are commonly employed for target fabrication. This study employs a new method for investigating the solid-state reactions between UAl<sub>2</sub> and the Al matrix during target fabrication using stepwise isothermal dilatometry (SID). The study focuses on the formation of UAl<sub>3</sub> and UAl<sub>4</sub>, which are less dense than UAl<sub>2</sub> and result in material expansion detected by the linear displacement, which relates to reaction conversion. By analyzing the linear expansion data from 560 °C to 630 °C, SID determines apparent activation energies and identifies the D2 diffusion rate model as the best fit, indicating a fast reaction rate along the UAl<sub>2</sub>/Al interfaces and highlighting the crucial role of interface diffusion in the process. This information is crucial for optimizing target fabrication and controlling the final composition of Mo-99 targets.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111763"},"PeriodicalIF":1.6,"publicationDate":"2025-03-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143577278","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

Soil-to-banana transfer factor of radionuclides in Lampung, Indonesia

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-03-01 DOI: 10.1016/j.apradiso.2025.111759

Ilma Dwi Winarni , Evans Azka Fajrianshah , Nicha Miranda , Riyaz Yusuf , Ramdhan Firman Saputra , Sesti Nurlatifah , Dhifana Mustachidah , Oumar Bobbo Modibo , Wahyudi , Radhia Pradana , Agus Nur Rachman , Ilsa Rosianna , Leons Rixson , Rusbani Kurniawan , Eka Djatnika Nugraha

This study estimates the soil-to-banana transfer factor of radionuclides in southern of Lampung, Indonesia, a region influenced by a large coal-fired power plant (CFPP) and other heavy industrial activities. This region is renowned for its banana productions, exceeding 11,000 tons annually for both local consumption (notably greater Jakarta) and export. Coal combustion in CFPP concentrates natural radionuclides from a series of uranium and thorium within the resulting ash. Soil and banana samples from Srengsem, Mataram, and Rangai Tri Tunggal villages were analyzed for ²²⁶Ra, ²³²Th, and ⁴⁰K using a calibrated P-type High-Purity Germanium (HPGe) detector. The study found average activity concentrations in soil were 26 ± 1 Bq kg⁻¹ for ²²⁶Ra, 28 ± 1 Bq kg⁻¹ for ²³²Th, and 368 ± 12 Bq kg⁻¹ for ⁴⁰K. In banana, ²²⁶Ra at 6 ± 1 Bq kg⁻¹ and ⁴⁰K at 288 ± 10 Bq kg⁻¹ (⁴⁰K) were detected, while ²³²Th below of limit detection. The transfer factors for ²²⁶Ra and ⁴⁰K were counted at 0.3 ± 0.2 and 1.6 ± 1.3, respectively, showing medium to high uptake. The estimated effective dose was significantly below the BAPETEN limit of 1 mSv year⁻¹, confirming that bananas cultivated in southern of Lampung area are safe for human consumption with minimal radiological impact. The findings underscore the critical insights into the safety of agricultural products produced in regions impacted by industrial activities and provides data for support the development of robust national food security management strategies.

{"title":"Soil-to-banana transfer factor of radionuclides in Lampung, Indonesia","authors":"Ilma Dwi Winarni , Evans Azka Fajrianshah , Nicha Miranda , Riyaz Yusuf , Ramdhan Firman Saputra , Sesti Nurlatifah , Dhifana Mustachidah , Oumar Bobbo Modibo , Wahyudi , Radhia Pradana , Agus Nur Rachman , Ilsa Rosianna , Leons Rixson , Rusbani Kurniawan , Eka Djatnika Nugraha","doi":"10.1016/j.apradiso.2025.111759","DOIUrl":"10.1016/j.apradiso.2025.111759","url":null,"abstract":"<div><div>This study estimates the soil-to-banana transfer factor of radionuclides in southern of Lampung, Indonesia, a region influenced by a large coal-fired power plant (CFPP) and other heavy industrial activities. This region is renowned for its banana productions, exceeding 11,000 tons annually for both local consumption (notably greater Jakarta) and export. Coal combustion in CFPP concentrates natural radionuclides from a series of uranium and thorium within the resulting ash. Soil and banana samples from Srengsem, Mataram, and Rangai Tri Tunggal villages were analyzed for <sup>226</sup>Ra, <sup>232</sup>Th, and <sup>40</sup>K using a calibrated P-type High-Purity Germanium (HPGe) detector. The study found average activity concentrations in soil were 26 ± 1 Bq kg<sup>−1</sup> for <sup>226</sup>Ra, 28 ± 1 Bq kg<sup>−1</sup> for <sup>232</sup>Th, and 368 ± 12 Bq kg<sup>−1</sup> for <sup>40</sup>K. In banana, <sup>226</sup>Ra at 6 ± 1 Bq kg<sup>−1</sup> and <sup>40</sup>K at 288 ± 10 Bq kg<sup>−1</sup> (<sup>40</sup>K) were detected, while <sup>232</sup>Th below of limit detection. The transfer factors for <sup>226</sup>Ra and <sup>40</sup>K were counted at 0.3 ± 0.2 and 1.6 ± 1.3, respectively, showing medium to high uptake. The estimated effective dose was significantly below the BAPETEN limit of 1 mSv year<sup>−1</sup>, confirming that bananas cultivated in southern of Lampung area are safe for human consumption with minimal radiological impact. The findings underscore the critical insights into the safety of agricultural products produced in regions impacted by industrial activities and provides data for support the development of robust national food security management strategies.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111759"},"PeriodicalIF":1.6,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143548001","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 measurement of the 80Kr(n,p)80mBr reaction cross-section for the d-T neutrons using highly enriched gas target

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-03-01 DOI: 10.1016/j.apradiso.2025.111751

Junhua Luo , Long He , Liang Zhou , Li Jiang

The cross sections of the ⁸⁰Kr(n,p)^80mBr reaction were measured through the secondary decay of the residual nucleus ^80mBr at the neutron energies of 13.59, 13.86, 14.13, 14.70, and 14.94 MeV. The characteristic gamma-ray of 616.3 keV energy emitted by ^80gBr was selected to determine the activity of the residual nucleus ^80mBr. The spherical target sample is a highly enriched, pure, and high-pressure ⁸⁰Kr isotope gas. The self-absorption of a 616.3 keV energy gamma ray, the geometry of the spherical sample, and the solid angle of the sample were corrected. The K-400 neutron generator of the China Academy of Engineering Physics (CAEP) was used for this experiment. The reaction T(d,n)⁴He provides quasi-monoenergetic neutrons. The neutron fluence was monitored using the monitor reaction ²⁷Al(n,α)²⁴Na, which has a threshold energy similar to ⁸⁰Kr(n,p)^80mBr reaction. The activity of the irradiated ⁸⁰Kr samples was determined using a high-purity germanium detector with high resolution and an off-line gamma spectrum technique. The covariance analysis was performed to determine the total uncertainty of the cross-section and the correlation matrix. The measured cross sections of ⁸⁰Kr(n,p)^80mBr reaction were compared with the previously reported experimental results, the theoretical results of the TALYS-1.96 simulation, and the evaluation results. In this experiment, the ⁸⁰Kr(n,p)^80mBr reaction cross section obtained over a wide energy range is extremely useful for testing the nuclear theoretical model and strengthening the nuclear database.

{"title":"The measurement of the 80Kr(n,p)80mBr reaction cross-section for the d-T neutrons using highly enriched gas target","authors":"Junhua Luo , Long He , Liang Zhou , Li Jiang","doi":"10.1016/j.apradiso.2025.111751","DOIUrl":"10.1016/j.apradiso.2025.111751","url":null,"abstract":"<div><div>The cross sections of the <sup>80</sup>Kr(n,p)<sup>80m</sup>Br reaction were measured through the secondary decay of the residual nucleus <sup>80m</sup>Br at the neutron energies of 13.59, 13.86, 14.13, 14.70, and 14.94 MeV. The characteristic gamma-ray of 616.3 keV energy emitted by <sup>80g</sup>Br was selected to determine the activity of the residual nucleus <sup>80m</sup>Br. The spherical target sample is a highly enriched, pure, and high-pressure <sup>80</sup>Kr isotope gas. The self-absorption of a 616.3 keV energy gamma ray, the geometry of the spherical sample, and the solid angle of the sample were corrected. The K-400 neutron generator of the China Academy of Engineering Physics (CAEP) was used for this experiment. The reaction T(d,n)<sup>4</sup>He provides quasi-monoenergetic neutrons. The neutron fluence was monitored using the monitor reaction <sup>27</sup>Al(n,α)<sup>24</sup>Na, which has a threshold energy similar to <sup>80</sup>Kr(n,p)<sup>80m</sup>Br reaction. The activity of the irradiated <sup>80</sup>Kr samples was determined using a high-purity germanium detector with high resolution and an off-line gamma spectrum technique. The covariance analysis was performed to determine the total uncertainty of the cross-section and the correlation matrix. The measured cross sections of <sup>80</sup>Kr(n,p)<sup>80m</sup>Br reaction were compared with the previously reported experimental results, the theoretical results of the TALYS-1.96 simulation, and the evaluation results. In this experiment, the <sup>80</sup>Kr(n,p)<sup>80m</sup>Br reaction cross section obtained over a wide energy range is extremely useful for testing the nuclear theoretical model and strengthening the nuclear database.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111751"},"PeriodicalIF":1.6,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143534069","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

Analysis of neutron induced reaction cross-section on 121,123Sb isotopes at neutron energy of 14.96 ± 0.03 MeV

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-02-28 DOI: 10.1016/j.apradiso.2025.111758

Shivani Sharma , Vandana , Pargin Bangotra , N.L. Singh , Mayur Mehta , R.K. Singh , R.J. Makwana , Mitul Abhangi , Ratnesh Kumar , Himanshu Sharma , Sudhirsinh Vala , K. Katovsky

The cross-section measurement of Antimony (Sb) is pivotal to modify or stagnate the rate of neutron flux in nuclear reactors. Neutron induced reaction cross-section data for isotopes of Sb is meagre as per reported in EXFOR. A comprehensive attempt has been made to analyse the reaction cross-section of ¹²¹Sb and ¹²³Sb at monoenergetic neutron energy of 14.96 ± 0.03 MeV. The experiment was performed at the Neutron and Ion Irradiation Facility, Institute for Plasma Research (IPR), Gujarat (India). The ²⁷Al(n,α)²⁴Na reaction is used to monitor the flux and to estimate the cross-section of (n,2n), (n,p) reactions using neutron activation technique. Monoenergetic neutrons generated by D-T fusion reaction were bombarded on the natural sample of Sb to induce radioactivity. A High Purity Germanium detector (HPGe) with a resolution of 2.1 keV at 1.33 MeV γ-ray energy of ⁶⁰Co based on GENIE software was used for the counting of emitted gamma photo peaks. Calculated results are compared with the existing studies from EXFOR. The cross-section values are estimated using TALYS-2.0 statistical code by employing different input parameters, along with the latest Evaluated Nuclear data libraries (ENDF/B-VIII.0, JEFF-3.3). To obtain more precise data, uncertainties from various parameters are propagated using the correlation coefficients among all the parameters. This systematic detailed covariance analysis helps to reduce the present discrepancies and to refine the nuclear data.

{"title":"Analysis of neutron induced reaction cross-section on 121,123Sb isotopes at neutron energy of 14.96 ± 0.03 MeV","authors":"Shivani Sharma , Vandana , Pargin Bangotra , N.L. Singh , Mayur Mehta , R.K. Singh , R.J. Makwana , Mitul Abhangi , Ratnesh Kumar , Himanshu Sharma , Sudhirsinh Vala , K. Katovsky","doi":"10.1016/j.apradiso.2025.111758","DOIUrl":"10.1016/j.apradiso.2025.111758","url":null,"abstract":"<div><div>The cross-section measurement of Antimony (Sb) is pivotal to modify or stagnate the rate of neutron flux in nuclear reactors. Neutron induced reaction cross-section data for isotopes of Sb is meagre as per reported in EXFOR. A comprehensive attempt has been made to analyse the reaction cross-section of <sup>121</sup>Sb and <sup>123</sup>Sb at monoenergetic neutron energy of 14.96 ± 0.03 MeV. The experiment was performed at the Neutron and Ion Irradiation Facility, Institute for Plasma Research (IPR), Gujarat (India). The <sup>27</sup>Al(n,α)<sup>24</sup>Na reaction is used to monitor the flux and to estimate the cross-section of (n,2n), (n,p) reactions using neutron activation technique. Monoenergetic neutrons generated by D-T fusion reaction were bombarded on the natural sample of Sb to induce radioactivity. A High Purity Germanium detector (HPGe) with a resolution of 2.1 keV at 1.33 MeV γ-ray energy of <sup>60</sup>Co based on GENIE software was used for the counting of emitted gamma photo peaks. Calculated results are compared with the existing studies from EXFOR. The cross-section values are estimated using TALYS-2.0 statistical code by employing different input parameters, along with the latest Evaluated Nuclear data libraries (ENDF/B-VIII.0, JEFF-3.3). To obtain more precise data, uncertainties from various parameters are propagated using the correlation coefficients among all the parameters. This systematic detailed covariance analysis helps to reduce the present discrepancies and to refine the nuclear data.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111758"},"PeriodicalIF":1.6,"publicationDate":"2025-02-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143548000","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

Radon progeny: Behaviour and influencing factors in indoor and outdoor environment

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-02-28 DOI: 10.1016/j.apradiso.2025.111760

Rosaline Mishra , R.P. Rout , R. Prajith , Jalaluddin S , A. Khan , B.K. Sapra

Radon progeny are the major contributor to inhalation dose to humans from natural sources of radiation. In addition, they are also used as tracers to study atmospheric phenomena. This makes it important to study the behaviour of Radon Progeny in both indoor and outdoor environment. In the present study, the progeny concentration, Radon gas concentration, unattached fraction are continuously measured for a period of 1 year in a ground floor room in Mumbai, both indoor and outdoor. The hourly average data for all months gave a clear picture of the diurnal and seasonal variation in progeny activity concentrations, unattached fractions and equilibrium factor in both environments. Average progeny concentration in the indoors was measured as ∼2–3 times higher that in the outdoors. The progeny activity in the outdoor environment was minimum in the rainy season (3.6 ± 1.2 Bq m⁻³), whereas that in indoors was minimum in summer season (7.5 ± 2.9 Bq m⁻³). Equilibrium factor in the indoor was obtained as V-shaped behavior with a minima in the afternoon, which was contrary to the inverted V-shaped measured in the outdoors. The night-time and day time variations highlight the influencing factors, like temperature, humidity, rainfall and turbulence.

{"title":"Radon progeny: Behaviour and influencing factors in indoor and outdoor environment","authors":"Rosaline Mishra , R.P. Rout , R. Prajith , Jalaluddin S , A. Khan , B.K. Sapra","doi":"10.1016/j.apradiso.2025.111760","DOIUrl":"10.1016/j.apradiso.2025.111760","url":null,"abstract":"<div><div>Radon progeny are the major contributor to inhalation dose to humans from natural sources of radiation. In addition, they are also used as tracers to study atmospheric phenomena. This makes it important to study the behaviour of Radon Progeny in both indoor and outdoor environment. In the present study, the progeny concentration, Radon gas concentration, unattached fraction are continuously measured for a period of 1 year in a ground floor room in Mumbai, both indoor and outdoor. The hourly average data for all months gave a clear picture of the diurnal and seasonal variation in progeny activity concentrations, unattached fractions and equilibrium factor in both environments. Average progeny concentration in the indoors was measured as ∼2–3 times higher that in the outdoors. The progeny activity in the outdoor environment was minimum in the rainy season (3.6 ± 1.2 Bq m<sup>−3</sup>), whereas that in indoors was minimum in summer season (7.5 ± 2.9 Bq m<sup>−3</sup>). Equilibrium factor in the indoor was obtained as V-shaped behavior with a minima in the afternoon, which was contrary to the inverted V-shaped measured in the outdoors. The night-time and day time variations highlight the influencing factors, like temperature, humidity, rainfall and turbulence.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111760"},"PeriodicalIF":1.6,"publicationDate":"2025-02-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143576796","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

Flexible Polyurethane - Tungsten oxide based composite for γ radiation shielding

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-02-27 DOI: 10.1016/j.apradiso.2025.111750

Prashant G. Ghule , G.T. Bholane , Rahul Kumar , R.P. Joshi , S.S. Dahiwale , P.N. Shelke , S.D. Dhole

The present work aims to develop and study a tungsten oxide containing polymer composite as an alternative for gamma radiation shielding. The seven polymer samples with different weight percentages (0 wt%, 5 wt%, 10 wt%, 20 wt%, 30 wt%, 40 wt%, and 50 wt%) of tungsten oxide (WO₃) were fabricated using a solvent casting technique, and their radiation shielding properties were assessed experimentally. The radiation shielding properties such as linear and mass attenuation coefficients, half value layer, tenth value layer, mean free path, radiation protection efficiency, effective atomic number, and effective electron density were evaluated for the gamma-ray energy ranges between 81 and 1408 keV using gamma-ray spectroscopy with an HPGe detector. Geant4 simulations were also performed to corroborate the consistency of the experimental results. Furthermore, a comparative analysis was conducted between the experimental findings simulated predictions, and theoretical data obtained from Phy-X/PSD online software. Among all composite samples, the sample with the highest wt% of WO₃ shows the highest mass attenuation coefficient of about 2.947 cm²/g and linear attenuation coefficient of about 4.8 cm⁻¹. Also, the comparison of MAC, LAC, and HVL results of the 50 wt% PU-WO₃ sample with other polymer-based bismuth oxide composites at 81 keV gamma photons shows better gamma radiation shielding efficiency which makes it a promising material for gamma radiation shielding applications.

{"title":"Flexible Polyurethane - Tungsten oxide based composite for γ radiation shielding","authors":"Prashant G. Ghule , G.T. Bholane , Rahul Kumar , R.P. Joshi , S.S. Dahiwale , P.N. Shelke , S.D. Dhole","doi":"10.1016/j.apradiso.2025.111750","DOIUrl":"10.1016/j.apradiso.2025.111750","url":null,"abstract":"<div><div>The present work aims to develop and study a tungsten oxide containing polymer composite as an alternative for gamma radiation shielding. The seven polymer samples with different weight percentages (0 wt%, 5 wt%, 10 wt%, 20 wt%, 30 wt%, 40 wt%, and 50 wt%) of tungsten oxide (WO<sub>3</sub>) were fabricated using a solvent casting technique, and their radiation shielding properties were assessed experimentally. The radiation shielding properties such as linear and mass attenuation coefficients, half value layer, tenth value layer, mean free path, radiation protection efficiency, effective atomic number, and effective electron density were evaluated for the gamma-ray energy ranges between 81 and 1408 keV using gamma-ray spectroscopy with an HPGe detector. Geant4 simulations were also performed to corroborate the consistency of the experimental results. Furthermore, a comparative analysis was conducted between the experimental findings simulated predictions, and theoretical data obtained from Phy-X/PSD online software. Among all composite samples, the sample with the highest wt% of WO<sub>3</sub> shows the highest mass attenuation coefficient of about 2.947 cm<sup>2</sup>/g and linear attenuation coefficient of about 4.8 cm<sup>−1</sup>. Also, the comparison of MAC, LAC, and HVL results of the 50 wt% PU-WO<sub>3</sub> sample with other polymer-based bismuth oxide composites at 81 keV gamma photons shows better gamma radiation shielding efficiency which makes it a promising material for gamma radiation shielding applications.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111750"},"PeriodicalIF":1.6,"publicationDate":"2025-02-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143511323","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

Background simulation of a low background gamma ray spectrometer with an array of five germanium detectors

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-02-27 DOI: 10.1016/j.apradiso.2025.111748

Jikai Chen , Zhi Zeng , Hao Ma , Mingkun Jing , Huaqiang Zhong , Hui Cao , Hui Zhang , Junli Li , Jianping Cheng

A new gamma ray spectrometer with an array of five germanium detectors, called ARGUS, is designed to screen and select materials used in rare-event search experiments. In this paper, we investigate the background characteristics of ARGUS using Monte Carlo simulation. The expected background count rate was found to reach the level of 10 counts per day per kg of germanium crystal (cpkd) in the energy region of 60 keV to 2700 keV. The minimum detectable activity (MDA) for germanium array was estimated via the maximum likelihood method. With an 100-day measurement of a 118.3 kg high purity copper sample, the MDA were calculated to be 28.8

μ

Bq/kg for ²¹²Pb (238 keV) and 32.8

μ

Bq/kg for ²¹⁴Bi (609 keV). The ARGUS is planned to be built in the China Jinping Underground Laboratory in 2025.

引用次数: 0

Assessing the impact of uncertainty in a VMAT plan for H&N cancer considering patient setup error (PSE)

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-02-27 DOI: 10.1016/j.apradiso.2025.111757

Arvind Kumar , Kiran Sharma , C.P. Bhatt , Awanish Sharma

In radiotherapy, accurate radiation dose delivery is critical, despite the uncertainties that can cause discrepancies between the prescribed and administered doses. This study examines the influence of uncertainties caused by patient positioning errors on dose accuracy and evaluates the potential consequences if these errors remain uncorrected. The investigation involves 670 treatment plans, including 10 clinically implemented plans and 660 with artificially induced uncertainties. These plans target patients undergoing volumetric arc therapy (VMAT) for various head & neck cancers using the Halcyon™ medical linear accelerator. Two scenarios are analyzed: one reflecting actual patient positioning shifts and another involving deliberate displacements ranging from 1 to 10 mm to assess the impact of uncertainty in a VMAT plan. Dosimetric validation is performed using EPID and the Octavius 4D phantom to introduce and assess the impact of these uncertainties. Results indicate that target coverage falls below the acceptable V95% threshold along the (X+, X-), (Y+, Y-), and (Z+, Z-) axes, when positioning errors exceed 5 mm. Additionally, both parotid glands are significantly affected by positioning uncertainties. Patient-specific quality assurance (PSQA) assessments confirm that positioning errors substantially affect the accuracy of dose delivery. To minimize uncertainties, strict adherence to recommended QA, clinical guidelines, imaging protocols, and other SOPs is crucial in clinical practice. Independent dosimetric audits are essential for evaluating the accuracy of dose delivery in treatment.

{"title":"Assessing the impact of uncertainty in a VMAT plan for H&N cancer considering patient setup error (PSE)","authors":"Arvind Kumar , Kiran Sharma , C.P. Bhatt , Awanish Sharma","doi":"10.1016/j.apradiso.2025.111757","DOIUrl":"10.1016/j.apradiso.2025.111757","url":null,"abstract":"<div><div>In radiotherapy, accurate radiation dose delivery is critical, despite the uncertainties that can cause discrepancies between the prescribed and administered doses. This study examines the influence of uncertainties caused by patient positioning errors on dose accuracy and evaluates the potential consequences if these errors remain uncorrected. The investigation involves 670 treatment plans, including 10 clinically implemented plans and 660 with artificially induced uncertainties. These plans target patients undergoing volumetric arc therapy (VMAT) for various head & neck cancers using the Halcyon™ medical linear accelerator. Two scenarios are analyzed: one reflecting actual patient positioning shifts and another involving deliberate displacements ranging from 1 to 10 mm to assess the impact of uncertainty in a VMAT plan. Dosimetric validation is performed using EPID and the Octavius 4D phantom to introduce and assess the impact of these uncertainties. Results indicate that target coverage falls below the acceptable V95% threshold along the (X+, X-), (Y+, Y-), and (Z+, Z-) axes, when positioning errors exceed 5 mm. Additionally, both parotid glands are significantly affected by positioning uncertainties. Patient-specific quality assurance (PSQA) assessments confirm that positioning errors substantially affect the accuracy of dose delivery. To minimize uncertainties, strict adherence to recommended QA, clinical guidelines, imaging protocols, and other SOPs is crucial in clinical practice. Independent dosimetric audits are essential for evaluating the accuracy of dose delivery in treatment.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111757"},"PeriodicalIF":1.6,"publicationDate":"2025-02-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143534067","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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