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Monte Carlo-based estimation of patient absorbed dose in 99mTc-DMSA, -MAG3, and -DTPA SPECT imaging using the University of Florida (UF) phantoms
IF 1.6 3区 工程技术
Applied Radiation and Isotopes Pub Date : 2025-03-06 DOI: 10.1016/j.apradiso.2025.111772
Zeynab Khoshyari , Reza Jahangir , Hashem Miri-Hakimabad , Najmeh Mohammadi , Hossein Arabi
{"title":"Monte Carlo-based estimation of patient absorbed dose in 99mTc-DMSA, -MAG3, and -DTPA SPECT imaging using the University of Florida (UF) phantoms","authors":"Zeynab Khoshyari ,&nbsp;Reza Jahangir ,&nbsp;Hashem Miri-Hakimabad ,&nbsp;Najmeh Mohammadi ,&nbsp;Hossein Arabi","doi":"10.1016/j.apradiso.2025.111772","DOIUrl":"10.1016/j.apradiso.2025.111772","url":null,"abstract":"<div><div>It is generally accepted that children's organs are more sensitive to radiation than adults, due to their growth rate. Therefore, evaluating the absorbed dose in children to avoid irrecoverable damage is highly crucial. In this work, absorbed dose by different organs of children within the SPECT imaging for the <sup>99m</sup>Tc-MAG3, <sup>99m</sup>Tc-DTPA, and <sup>99m</sup>Tc-DMSA that are commonly employed for pediatric patients, were estimated through the use of Monte Carlo simulation and the University of Florida's (UF) voxel-wise phantoms at the ages of 4, 8, 11, and 14-years old. The results showed that the highest absorbed dose was by kidneys and when <sup>99m</sup>Tc-DMSA was used. Also, the highest and lowest absorbed dose in the organs occurred when <sup>99m</sup>Tc-DMSA and <sup>99m</sup>Tc-MAG3 were used, respectively. The simulation results were in good agreement with the ICRP 128 data.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111772"},"PeriodicalIF":1.6,"publicationDate":"2025-03-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143593090","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
Resilient STR loci under gamma radiation: A preliminary study on DNA stability in buccal swabs
IF 1.6 3区 工程技术
Applied Radiation and Isotopes Pub Date : 2025-03-06 DOI: 10.1016/j.apradiso.2025.111762
Amani Kraishan , Ahmad M. Refaat , Jenan A. Almhaini , Alaa Saeed Bazuhair , Saeed M. Al-Qahtani , Marwan A. Althomali , Hatem Al-Ameryeen , Ali H. Alomari , Abdul-Wali Ajlouni
{"title":"Resilient STR loci under gamma radiation: A preliminary study on DNA stability in buccal swabs","authors":"Amani Kraishan ,&nbsp;Ahmad M. Refaat ,&nbsp;Jenan A. Almhaini ,&nbsp;Alaa Saeed Bazuhair ,&nbsp;Saeed M. Al-Qahtani ,&nbsp;Marwan A. Althomali ,&nbsp;Hatem Al-Ameryeen ,&nbsp;Ali H. Alomari ,&nbsp;Abdul-Wali Ajlouni","doi":"10.1016/j.apradiso.2025.111762","DOIUrl":"10.1016/j.apradiso.2025.111762","url":null,"abstract":"<div><div>This study explores how gamma radiation affects DNA concentration and the stability of autosomal short tandem repeat (STR) markers in buccal swab samples. A total of 160 swabs from 20 volunteers were exposed to therapeutic radiation doses ranging from 1 to 80 Gy. The results revealed a clear dose-dependent decrease in DNA concentration, indicating significant DNA damage as radiation increased. Despite this, the autosomal STR markers remained stable across all doses, demonstrating their robustness against radiation-induced damage. These findings are crucial for clinical and forensic applications, confirming that STR profiling remains reliable for cancer patients undergoing radiation therapy and in forensic cases involving irradiated DNA. The study emphasizes the value of STR markers in genetic analysis under challenging conditions and highlights the need for further research on their long-term stability in diverse biological contexts.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111762"},"PeriodicalIF":1.6,"publicationDate":"2025-03-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143577279","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
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
Applied Radiation and Isotopes Pub Date : 2025-03-06 DOI: 10.1016/j.apradiso.2025.111765
Bassam T. Al-Azraq , Noor Ali Hameed
{"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 ,&nbsp;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
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
{"title":"Analysis of cement raw materials radioactivity in Chongqing","authors":"Feng Wang ,&nbsp;Shang Geng ,&nbsp;Chuncen Wu ,&nbsp;Hengyan Du ,&nbsp;Xiuqin Zhang ,&nbsp;Yifan Song ,&nbsp;Yang Chen ,&nbsp;Mingxiao Wang ,&nbsp;Guoqiang Wang ,&nbsp;Tianya Huang ,&nbsp;Xue Zhao ,&nbsp;Fei Li ,&nbsp;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
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
{"title":"Investigating solid-state reactions in UAl2-Al dispersions for Mo-99 target fabrication","authors":"Thomaz Augusto Guisard Restivo ,&nbsp;Giovanni de Lima Cabral Conturbia ,&nbsp;Elita Fontenele Urano de Carvalho ,&nbsp;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
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
{"title":"Soil-to-banana transfer factor of radionuclides in Lampung, Indonesia","authors":"Ilma Dwi Winarni ,&nbsp;Evans Azka Fajrianshah ,&nbsp;Nicha Miranda ,&nbsp;Riyaz Yusuf ,&nbsp;Ramdhan Firman Saputra ,&nbsp;Sesti Nurlatifah ,&nbsp;Dhifana Mustachidah ,&nbsp;Oumar Bobbo Modibo ,&nbsp;Wahyudi ,&nbsp;Radhia Pradana ,&nbsp;Agus Nur Rachman ,&nbsp;Ilsa Rosianna ,&nbsp;Leons Rixson ,&nbsp;Rusbani Kurniawan ,&nbsp;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
Applied Radiation and Isotopes Pub Date : 2025-03-01 DOI: 10.1016/j.apradiso.2025.111751
Junhua Luo , Long He , Liang Zhou , Li Jiang
{"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 ,&nbsp;Long He ,&nbsp;Liang Zhou ,&nbsp;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
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
{"title":"Analysis of neutron induced reaction cross-section on 121,123Sb isotopes at neutron energy of 14.96 ± 0.03 MeV","authors":"Shivani Sharma ,&nbsp;Vandana ,&nbsp;Pargin Bangotra ,&nbsp;N.L. Singh ,&nbsp;Mayur Mehta ,&nbsp;R.K. Singh ,&nbsp;R.J. Makwana ,&nbsp;Mitul Abhangi ,&nbsp;Ratnesh Kumar ,&nbsp;Himanshu Sharma ,&nbsp;Sudhirsinh Vala ,&nbsp;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
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
{"title":"Radon progeny: Behaviour and influencing factors in indoor and outdoor environment","authors":"Rosaline Mishra ,&nbsp;R.P. Rout ,&nbsp;R. Prajith ,&nbsp;Jalaluddin S ,&nbsp;A. Khan ,&nbsp;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
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
{"title":"Flexible Polyurethane - Tungsten oxide based composite for γ radiation shielding","authors":"Prashant G. Ghule ,&nbsp;G.T. Bholane ,&nbsp;Rahul Kumar ,&nbsp;R.P. Joshi ,&nbsp;S.S. Dahiwale ,&nbsp;P.N. Shelke ,&nbsp;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
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