In radiation dosimetry, achieving electronic equilibrium is vital for accurate dose measurements in radioprotection. This study investigates the effect of Poly Methyl Methacrylate (PMMA) layers, known by its chemical formula C5H8O2 and a density of 1.19 g/cm³ (PNNL, 2011), on electronic equilibrium for the calibration of radiation protection instruments, focusing on photon beams of varying energies. Using DOSIMEX 2.0 simulation software, we modeled the influence of PMMA thickness on calibration factors across different X-ray and gamma-ray beam energies. Experimental validation with Cs-137 and Co-60 sources confirmed the reliability of the simulation. Our results highlight that while PMMA layers have a minimal impact on calibration for higher-energy beams, their role becomes significant for energies below 40 keV. For X-ray beams (From 30 to 140 kV), the results show minimal calibration factor deviation (<1.6%), whereas radionuclide beams exhibit more significant variations (4.1%), necessitating customized calibration approaches. This study underscores the importance of adhering to ISO 4037-3 standards in radioprotection, particularly in low-energy scenarios, to ensure the precision of calibration procedures and optimize radiation protection practices. Furthermore, based on the results obtained, the absence of PMMA does not have a dramatic effect on the calibration of X-ray radiation instruments, whereas for gamma-ray beams, it has a significant impact.
{"title":"Optimizing radiation dosimetry: Impact of PMMA layers on electronic equilibrium for the calibration of radiation protection instruments","authors":"Taibi Zidouz , Abdelatif Talbi , El Mahjoub Chakir , Elmehdi Alibrahmi , Mohammed Zaryah , Abderahim Allach , Abdessamad Didi , Abdelwahab Abarane","doi":"10.1016/j.apradiso.2024.111588","DOIUrl":"10.1016/j.apradiso.2024.111588","url":null,"abstract":"<div><div>In radiation dosimetry, achieving electronic equilibrium is vital for accurate dose measurements in radioprotection. This study investigates the effect of Poly Methyl Methacrylate (PMMA) layers, known by its chemical formula C<sub>5</sub>H<sub>8</sub>O<sub>2</sub> and a density of 1.19 g/cm³ (PNNL, 2011), on electronic equilibrium for the calibration of radiation protection instruments, focusing on photon beams of varying energies. Using DOSIMEX 2.0 simulation software, we modeled the influence of PMMA thickness on calibration factors across different X-ray and gamma-ray beam energies. Experimental validation with Cs-137 and Co-60 sources confirmed the reliability of the simulation. Our results highlight that while PMMA layers have a minimal impact on calibration for higher-energy beams, their role becomes significant for energies below 40 keV. For X-ray beams (From 30 to 140 kV), the results show minimal calibration factor deviation (<1.6%), whereas radionuclide beams exhibit more significant variations (4.1%), necessitating customized calibration approaches. This study underscores the importance of adhering to ISO 4037-3 standards in radioprotection, particularly in low-energy scenarios, to ensure the precision of calibration procedures and optimize radiation protection practices. Furthermore, based on the results obtained, the absence of PMMA does not have a dramatic effect on the calibration of X-ray radiation instruments, whereas for gamma-ray beams, it has a significant impact.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"215 ","pages":"Article 111588"},"PeriodicalIF":1.6,"publicationDate":"2024-11-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142646803","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-11-13DOI: 10.1016/j.apradiso.2024.111587
Abdulilah Mohammad Mayet , Seyed Mehdi Alizadeh , Muneer Parayangat , John William Grimaldo Guerrero , M. Ramkumar Raja , Mohammed Abdul Muqeet , Salman Arafath Mohammed
This work presents a novel technique to improve oil pipeline monitoring capabilities, a vital activity in the oil and gas sector. Using Monte Carlo simulations, the work meticulously records data from a pipeline testing environment with various petroleum products and volume ratios. We apply the presented technique to mix four petroleum products—ethylene glycol, gasoline, crude oil, and gasoil—in different volumetric fractions to precisely determine their volume ratios. Many characteristics of the signal, including its mean, standard deviation, autocorrelation, zero-crossing rate, dominant frequency, power spectral density, harmonic-to-noise ratio, cross-frequency coupling, peak-to-peak amplitude, and fall time, are extracted after data collection. To select optimal features, an innovative approach utilizing ant colony optimization is deployed, systematically identifying the most informative feature combinations for volumetric ratio prediction. These meticulously chosen features serve as inputs to a multilayer perceptron (MLP) neural network tasked with accurately determining the volume ratio of the pipeline contents. Remarkably, the methodology showcases remarkable efficacy, with the root mean square error (RMSE) in volume ratio determination found to be less than 0.52. This significant finding not only underscores the robustness of the proposed approach but also promises to revolutionize pipeline monitoring techniques, offering unprecedented accuracy and efficiency in oil industry operations. This research thus represents a pivotal advancement in the field, with far-reaching implications for both academic research and practical applications within the oil and gas sector.
{"title":"ACO-based feature selection and neural network modeling for accurate gamma-radiation based pipeline monitoring in the oil industry","authors":"Abdulilah Mohammad Mayet , Seyed Mehdi Alizadeh , Muneer Parayangat , John William Grimaldo Guerrero , M. Ramkumar Raja , Mohammed Abdul Muqeet , Salman Arafath Mohammed","doi":"10.1016/j.apradiso.2024.111587","DOIUrl":"10.1016/j.apradiso.2024.111587","url":null,"abstract":"<div><div>This work presents a novel technique to improve oil pipeline monitoring capabilities, a vital activity in the oil and gas sector. Using Monte Carlo simulations, the work meticulously records data from a pipeline testing environment with various petroleum products and volume ratios. We apply the presented technique to mix four petroleum products—ethylene glycol, gasoline, crude oil, and gasoil—in different volumetric fractions to precisely determine their volume ratios. Many characteristics of the signal, including its mean, standard deviation, autocorrelation, zero-crossing rate, dominant frequency, power spectral density, harmonic-to-noise ratio, cross-frequency coupling, peak-to-peak amplitude, and fall time, are extracted after data collection. To select optimal features, an innovative approach utilizing ant colony optimization is deployed, systematically identifying the most informative feature combinations for volumetric ratio prediction. These meticulously chosen features serve as inputs to a multilayer perceptron (MLP) neural network tasked with accurately determining the volume ratio of the pipeline contents. Remarkably, the methodology showcases remarkable efficacy, with the root mean square error (RMSE) in volume ratio determination found to be less than 0.52. This significant finding not only underscores the robustness of the proposed approach but also promises to revolutionize pipeline monitoring techniques, offering unprecedented accuracy and efficiency in oil industry operations. This research thus represents a pivotal advancement in the field, with far-reaching implications for both academic research and practical applications within the oil and gas sector.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"215 ","pages":"Article 111587"},"PeriodicalIF":1.6,"publicationDate":"2024-11-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142643272","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
This study investigates radon concentration in drinking water from twenty samples collected at two tertiary Institutions in Ikorodu, Lagos State, using the RAD-7 detector. The objective is to evaluate the health risks associated with radon exposure, a known carcinogen linked to lung and stomach cancer. Radon in drinking water contributes to approximately 168 cancer deaths annually, predominantly from lung cancer due to inhalation of radon released indoors and stomach cancer from ingesting contaminated water. The measured radon concentrations ranged from 4.5 ± 1.1 Bq/m³ to 25.5 ± 2.1 Bq/m³, with 70% of samples exceeding the EPA's maximum contamination level of 11.1 Bq/L. Despite these high levels, the annual effective doses from ingestion and inhalation varied from 0.4545 to 24.37 μSv/y, remaining below the global average of 300 μSv/y and WHO limit of 100 μSv/y. While the presence of radon in Ikorodu's water sources indicates a radiological risk, the associated health risks are comparatively low according to international standards. These findings underscore the importance of ongoing monitoring and potential mitigation measures to ensure the continued safety of drinking water in the region.
{"title":"Comprehensive investigation of carcinogenic radon levels in water within the Ikorodu axis of Lagos State, Nigeria","authors":"Olaoye Morohunfoluwa Adeola , Hyam Nazmy Bader Khalaf , Okedeyi Sodiq , Mostafa Y.A. Mostafa , Howaida Mansour","doi":"10.1016/j.apradiso.2024.111585","DOIUrl":"10.1016/j.apradiso.2024.111585","url":null,"abstract":"<div><div>This study investigates radon concentration in drinking water from twenty samples collected at two tertiary Institutions in Ikorodu, Lagos State, using the RAD-7 detector. The objective is to evaluate the health risks associated with radon exposure, a known carcinogen linked to lung and stomach cancer. Radon in drinking water contributes to approximately 168 cancer deaths annually, predominantly from lung cancer due to inhalation of radon released indoors and stomach cancer from ingesting contaminated water. The measured radon concentrations ranged from 4.5 ± 1.1 Bq/m³ to 25.5 ± 2.1 Bq/m³, with 70% of samples exceeding the EPA's maximum contamination level of 11.1 Bq/L. Despite these high levels, the annual effective doses from ingestion and inhalation varied from 0.4545 to 24.37 μSv/y, remaining below the global average of 300 μSv/y and WHO limit of 100 μSv/y. While the presence of radon in Ikorodu's water sources indicates a radiological risk, the associated health risks are comparatively low according to international standards. These findings underscore the importance of ongoing monitoring and potential mitigation measures to ensure the continued safety of drinking water in the region.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"215 ","pages":"Article 111585"},"PeriodicalIF":1.6,"publicationDate":"2024-11-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142613769","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-11-10DOI: 10.1016/j.apradiso.2024.111586
Martin Schulc , Evžen Novák , Jan Šimon , Alena Krechlerová , Michal Košťál , Roberto Capote
We have investigated following capture reactions: 197Au(n,g)198Au, 63Cu(n,g)64Cu, 45Sc(n,g)46Sc, 181Ta(n,g)182Ta, 140Ce(n,g)141Ce, 139La(n,g)140La, 176Yb(n,g)177Yb, 55Mn(n,g)56Mn, and 141Pr(n,g)142Pr in a standard 252Cf(s.f.) neutron field. The experimentally derived reaction rates were compared with calculations using state-of-the-art libraries IRDFF-II, ENDF/B-VIII.0, JENDL-5 and JEFF-3.3 performed in MCNP6.2 transport code. The experiment was focused on capture reactions in high energy neutron range. To suppress scattered low energy neutrons, all activation materials were enclosed by a spherical cadmium surface of 30 cm in diameter. Experimentally derived reaction rates of 197Au(n,g)198Au, 63Cu(n,g)64Cu reactions agree with calculations using all state-of-the-art nuclear data libraries. The highest discrepancies were found when evaluating 139La(n,g)140La and 55Mn(n,g)56Mn reactions utilizing all libraries. Experimental reaction rates applying data from the JENDL-5 library agree very well with the results of other reactions except for the 45Sc(n,g)46Sc reaction. 181Ta(n,g)182Ta reaction rate does not agree within uncertainties using any library. The 176Yb(n,g)177Yb reaction rate agrees reasonably well only when performing calculation using JENDL-5 and ENDF/B-VIII.0 libraries, unlike JEFF-3.3 library. 140Ce(n,g)141Ce and 141Pr(n,g)142Pr reaction rates applying JEFF-3.3 and ENDF/B-VIII.0 libraries do not agree within uncertainties.
{"title":"Validation of capture reactions cross sections in 252Cf(s.f.) neutron field","authors":"Martin Schulc , Evžen Novák , Jan Šimon , Alena Krechlerová , Michal Košťál , Roberto Capote","doi":"10.1016/j.apradiso.2024.111586","DOIUrl":"10.1016/j.apradiso.2024.111586","url":null,"abstract":"<div><div>We have investigated following capture reactions: <sup>197</sup>Au(n,g)<sup>198</sup>Au, <sup>63</sup>Cu(n,g)<sup>64</sup>Cu, <sup>45</sup>Sc(n,g)<sup>46</sup>Sc, <sup>181</sup>Ta(n,g)<sup>182</sup>Ta, <sup>140</sup>Ce(n,g)<sup>141</sup>Ce, <sup>139</sup>La(n,g)<sup>140</sup>La, <sup>176</sup>Yb(n,g)<sup>177</sup>Yb, <sup>55</sup>Mn(n,g)<sup>56</sup>Mn, and <sup>141</sup>Pr(n,g)<sup>142</sup>Pr in a standard <sup>252</sup>Cf(s.f.) neutron field. The experimentally derived reaction rates were compared with calculations using state-of-the-art libraries IRDFF-II, ENDF/B-VIII.0, JENDL-5 and JEFF-3.3 performed in MCNP6.2 transport code. The experiment was focused on capture reactions in high energy neutron range. To suppress scattered low energy neutrons, all activation materials were enclosed by a spherical cadmium surface of 30 cm in diameter. Experimentally derived reaction rates of <sup>197</sup>Au(n,g)<sup>198</sup>Au, <sup>63</sup>Cu(n,g)<sup>64</sup>Cu reactions agree with calculations using all state-of-the-art nuclear data libraries. The highest discrepancies were found when evaluating <sup>139</sup>La(n,g)<sup>140</sup>La and <sup>55</sup>Mn(n,g)<sup>56</sup>Mn reactions utilizing all libraries. Experimental reaction rates applying data from the JENDL-5 library agree very well with the results of other reactions except for the <sup>45</sup>Sc(n,g)<sup>46</sup>Sc reaction. <sup>181</sup>Ta(n,g)<sup>182</sup>Ta reaction rate does not agree within uncertainties using any library. The <sup>176</sup>Yb(n,g)<sup>177</sup>Yb reaction rate agrees reasonably well only when performing calculation using JENDL-5 and ENDF/B-VIII.0 libraries, unlike JEFF-3.3 library. <sup>140</sup>Ce(n,g)<sup>141</sup>Ce and <sup>141</sup>Pr(n,g)<sup>142</sup>Pr reaction rates applying JEFF-3.3 and ENDF/B-VIII.0 libraries do not agree within uncertainties.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"215 ","pages":"Article 111586"},"PeriodicalIF":1.6,"publicationDate":"2024-11-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142613786","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-11-06DOI: 10.1016/j.apradiso.2024.111584
Ravindra Shende , S.J. Dhoble , Umesh Gayake
Study aimed at Monte Carlo (MC) modeling and dosimetric validation of GammaMed Plus 192Ir source for high dose rate brachytherapy using Geant4 code in TOPAS. Study investigated the several TG-43 guided dosimetric parameters for brachytherapy dose calculation. The excellent agreement was found between simulated and published data. The simulated MC dataset can be served as reference and fed into Treatment planning system (TPS) to verify brachytherapy dose calculation. Present MC modeling of brachytherapy source can be availed in further patient specific studies involving MC simulation.
研究旨在使用 TOPAS 中的 Geant4 代码对用于高剂量率近距离放射治疗的 GammaMed Plus 192Ir 源进行蒙特卡罗（MC）建模和剂量学验证。研究调查了用于近距离放射剂量计算的几个 TG-43 引导剂量学参数。结果发现，模拟数据与已公布的数据非常吻合。模拟的 MC 数据集可作为参考，并输入治疗计划系统 (TPS) 以验证近距离治疗剂量计算。目前的近距离放射源 MC 建模可用于进一步的特定患者 MC 模拟研究。
{"title":"Monte Carlo modeling and dosimetric validation of GammaMed Plus 192Ir source for HDR brachytherapy application using TOPAS","authors":"Ravindra Shende , S.J. Dhoble , Umesh Gayake","doi":"10.1016/j.apradiso.2024.111584","DOIUrl":"10.1016/j.apradiso.2024.111584","url":null,"abstract":"<div><div>Study aimed at Monte Carlo (MC) modeling and dosimetric validation of GammaMed Plus <sup>192</sup>Ir source for high dose rate brachytherapy using Geant4 code in TOPAS. Study investigated the several TG-43 guided dosimetric parameters for brachytherapy dose calculation. The excellent agreement was found between simulated and published data. The simulated MC dataset can be served as reference and fed into Treatment planning system (TPS) to verify brachytherapy dose calculation. Present MC modeling of brachytherapy source can be availed in further patient specific studies involving MC simulation.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"215 ","pages":"Article 111584"},"PeriodicalIF":1.6,"publicationDate":"2024-11-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142638067","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-11-06DOI: 10.1016/j.apradiso.2024.111582
Rajesh Sankhla , Deepak K. Akar , Rahul Roy , M.S. Kulkarni , I.S. Singh , P. Pradosh , Pramilla D. Sawant , Probal Chaudhury
An automated standing type Quick Scan Whole Body Monitor (QS-WBM) has been developed for the measurement of internal radioactive contamination due to high energy photon (HEP) emitters (Eϒ >200 keV). Individuals are monitored while standing on a platform inside QS-WBM at specified reference position. Instances may occur where individuals deviate from their monitoring position, potentially leading to errors in the measurement of the body content. Positional inaccuracies are estimated in three potential scenarios: lateral displacement of the individual, movement perpendicular to the detector face, and forward bending of the torso. The Monte Carlo particle transport code FLUKA is used for estimation of efficiencies for selected radionuclides across various geometrical positions for adult male radiation workers. Approximately, 8% variation in calibration factors (CFs) is noted for lateral movements up to 15 cm from the centerline regardless of the energy, while perpendicular movements from reference position exhibit variations ranging from 14 to 60 %. This study helps in quantifying uncertainties in the estimation of body content and dose, arising from deviations in position of individuals in QS-WBM enclosure during monitoring.
{"title":"Investigation on the impact of the spatial arrangement of individuals in a standing-type in-vivo monitoring system","authors":"Rajesh Sankhla , Deepak K. Akar , Rahul Roy , M.S. Kulkarni , I.S. Singh , P. Pradosh , Pramilla D. Sawant , Probal Chaudhury","doi":"10.1016/j.apradiso.2024.111582","DOIUrl":"10.1016/j.apradiso.2024.111582","url":null,"abstract":"<div><div>An automated standing type Quick Scan Whole Body Monitor (QS-WBM) has been developed for the measurement of internal radioactive contamination due to high energy photon (HEP) emitters (E<sub>ϒ</sub> >200 keV). Individuals are monitored while standing on a platform inside QS-WBM at specified reference position. Instances may occur where individuals deviate from their monitoring position, potentially leading to errors in the measurement of the body content. Positional inaccuracies are estimated in three potential scenarios: lateral displacement of the individual, movement perpendicular to the detector face, and forward bending of the torso. The Monte Carlo particle transport code FLUKA is used for estimation of efficiencies for selected radionuclides across various geometrical positions for adult male radiation workers. Approximately, 8% variation in calibration factors (CFs) is noted for lateral movements up to 15 cm from the centerline regardless of the energy, while perpendicular movements from reference position exhibit variations ranging from 14 to 60 %. This study helps in quantifying uncertainties in the estimation of body content and dose, arising from deviations in position of individuals in QS-WBM enclosure during monitoring.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"215 ","pages":"Article 111582"},"PeriodicalIF":1.6,"publicationDate":"2024-11-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142613779","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-11-06DOI: 10.1016/j.apradiso.2024.111583
Khalid M. Aloufi , Moawia Gameraddin , Fahad H. Alhazmi , Iesa S. Almazroui , Hamid Osman , Mayeen Uddin Khandaker
Background
Nuclear medicine diagnostic and treatment procedures represent significant sources of ionizing radiation exposure for both staff and patients. Consequently, assessing and optimizing radiation doses are crucial to minimize potential side effects.
Aim
This study seeks to evaluate the effective radiation doses associated with common diagnostic and treatment procedures, as well as propose diagnostic reference levels (DRLs), within two nuclear medicine centers in Madinah, Saudi Arabia.
Methodology
Data from 445 patients were gathered from two nuclear medicine centers in the Madinah region of Saudi Arabia. The data were categorized based on the type of nuclear medicine (NM) procedure, the chemical composition of the administered radiopharmaceutical, as well as patient age and weight. Effective radiation doses for prevalent NM procedures were computed, and suggested DRLs were formulated.
Results
Effective radiation doses were analyzed for 16 adult and 2 pediatric NM procedures (divided into 8 groups). The effective radiation doses for adult diagnostic nuclear medicine procedures range from 0.05 mSv (Nanocoloid) to 29 mSv (67Ga-citrate). For pediatric procedures, the doses range from 0.80 mSv (5-year-old undergoing renal DTPA) to 1.6 mSv (1-year-old undergoing renal DMSA). Furthermore, DRL values were determined for both adult and pediatric NM procedures. The study's findings demonstrated a high degree of concordance between effective radiation doses and DRL values, aligning well with previously published research.
Conclusion
While the effective radiation doses outlined in this study were generally within acceptable limits and consistent with prior research findings, optimizing radiation doses remains imperative, particularly for pediatric NM procedures.
{"title":"Assessing radiation doses and proposing DRLs for nuclear medicine procedures for pediatric and adult patients in Madinah, Saudi Arabia","authors":"Khalid M. Aloufi , Moawia Gameraddin , Fahad H. Alhazmi , Iesa S. Almazroui , Hamid Osman , Mayeen Uddin Khandaker","doi":"10.1016/j.apradiso.2024.111583","DOIUrl":"10.1016/j.apradiso.2024.111583","url":null,"abstract":"<div><h3>Background</h3><div>Nuclear medicine diagnostic and treatment procedures represent significant sources of ionizing radiation exposure for both staff and patients. Consequently, assessing and optimizing radiation doses are crucial to minimize potential side effects.</div></div><div><h3>Aim</h3><div>This study seeks to evaluate the effective radiation doses associated with common diagnostic and treatment procedures, as well as propose diagnostic reference levels (DRLs), within two nuclear medicine centers in Madinah, Saudi Arabia.</div></div><div><h3>Methodology</h3><div>Data from 445 patients were gathered from two nuclear medicine centers in the Madinah region of Saudi Arabia. The data were categorized based on the type of nuclear medicine (NM) procedure, the chemical composition of the administered radiopharmaceutical, as well as patient age and weight. Effective radiation doses for prevalent NM procedures were computed, and suggested DRLs were formulated.</div></div><div><h3>Results</h3><div>Effective radiation doses were analyzed for 16 adult and 2 pediatric NM procedures (divided into 8 groups). The effective radiation doses for adult diagnostic nuclear medicine procedures range from 0.05 mSv (Nanocoloid) to 29 mSv (67Ga-citrate). For pediatric procedures, the doses range from 0.80 mSv (5-year-old undergoing renal DTPA) to 1.6 mSv (1-year-old undergoing renal DMSA). Furthermore, DRL values were determined for both adult and pediatric NM procedures. The study's findings demonstrated a high degree of concordance between effective radiation doses and DRL values, aligning well with previously published research.</div></div><div><h3>Conclusion</h3><div>While the effective radiation doses outlined in this study were generally within acceptable limits and consistent with prior research findings, optimizing radiation doses remains imperative, particularly for pediatric NM procedures.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"215 ","pages":"Article 111583"},"PeriodicalIF":1.6,"publicationDate":"2024-11-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142613765","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-11-06DOI: 10.1016/j.apradiso.2024.111581
Vladislav A. Zobnin , Boris L. Zhuikov , Aleksandr N. Vasiliev , Gleb A. Polnyakov
The article presents a novel gas-chemical approach for 225Ac/213Bi generators, which provides effective separation of 213Bi from parent 225Ac. The main problem with the generators of high activity is the radiation stability of sorbents, which is not substantial in this gas-chemical method of separation, where only radiationally stable inorganic materials are used. The approach includes heating at high temperature (about 900–1000 °C) 225Ac sample deposited on a backing material (Nb, quartz glass, stainless steel) in hydrogen-containing inert gas flow. Actinium is non-volatile in these conditions, while Bi sublimes and is deposited on a catcher-foil along a temperature gradient. Niobium was found to be the best of the used material for both the starting backing and catcher-foil. The effective activation energy of carrier-free amount of Bi-sublimation from Nb-backing as 102 ± 9 kJ/mol has been calculated, and standard enthalpy of desorption of Bi on Nb from thermochromatographic data has been evaluated as 269 ± 13 kJ/mol 213Bi may be recovered for the consequent preparation of radiopharmaceuticals by washing from the catcher-foil surface. The gas-chemical method has been demonstrated to be a promising approach for 225Ac/213Bi generators for its application in targeted alpha therapy.
{"title":"Gas-chemical approach to 225Ac/213Bi radionuclide generator for medical application","authors":"Vladislav A. Zobnin , Boris L. Zhuikov , Aleksandr N. Vasiliev , Gleb A. Polnyakov","doi":"10.1016/j.apradiso.2024.111581","DOIUrl":"10.1016/j.apradiso.2024.111581","url":null,"abstract":"<div><div>The article presents a novel gas-chemical approach for <sup>225</sup>Ac/<sup>213</sup>Bi generators, which provides effective separation of <sup>213</sup>Bi from parent <sup>225</sup>Ac. The main problem with the generators of high activity is the radiation stability of sorbents, which is not substantial in this gas-chemical method of separation, where only radiationally stable inorganic materials are used. The approach includes heating at high temperature (about 900–1000 °C) <sup>225</sup>Ac sample deposited on a backing material (Nb, quartz glass, stainless steel) in hydrogen-containing inert gas flow. Actinium is non-volatile in these conditions, while Bi sublimes and is deposited on a catcher-foil along a temperature gradient. Niobium was found to be the best of the used material for both the starting backing and catcher-foil. The effective activation energy of carrier-free amount of Bi-sublimation from Nb-backing as 102 ± 9 kJ/mol has been calculated, and standard enthalpy of desorption of Bi on Nb from thermochromatographic data has been evaluated as 269 ± 13 kJ/mol <sup>213</sup>Bi may be recovered for the consequent preparation of radiopharmaceuticals by washing from the catcher-foil surface. The gas-chemical method has been demonstrated to be a promising approach for <sup>225</sup>Ac/<sup>213</sup>Bi generators for its application in targeted alpha therapy.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"215 ","pages":"Article 111581"},"PeriodicalIF":1.6,"publicationDate":"2024-11-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142613777","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-11-06DOI: 10.1016/j.apradiso.2024.111580
Austin D. Nelson, Adam M. Clark, Thomas L. Bailey, Lauren K. Callahan, Philippe Collon
The radioisotopes of 43Sc and 44Sc are promising in the field of theranostics for their role as β+ emitters in theranostic pairs with 47Sc. Production of these isotopes through various nuclear reactions using either cyclotrons or linear accelerators is of particular interest and previous studies have provided results using accelerated beams of protons, deuterons, and alpha particles. A novel production technique, using an ion source cathode packed with natural calcium fluoride material and irradiated with a 3He beam, was tested at the Nuclear Science Laboratory at the University of Notre Dame in order to initially study the production of 41Ca. Gamma-ray spectrometry revealed presence of 43Sc and 44Sc in the target, and allowed for the first measurement of their yield due to reactions of 3He on natural calcium. The calculated thick target yields of 43Sc and 44gSc from the reactions natCa(3He,x)43Sc and natCa(3He,x)44gSc are compared to theoretical results using TALYS cross section models. Overall, results agree well with models at lower beam energies but tend to diverge at higher energies.
{"title":"Production of 43Sc and 44gSc from natural CaF2 material using an FN Tandem accelerator","authors":"Austin D. Nelson, Adam M. Clark, Thomas L. Bailey, Lauren K. Callahan, Philippe Collon","doi":"10.1016/j.apradiso.2024.111580","DOIUrl":"10.1016/j.apradiso.2024.111580","url":null,"abstract":"<div><div>The radioisotopes of <sup>43</sup>Sc and <sup>44</sup>Sc are promising in the field of theranostics for their role as β<sup>+</sup> emitters in theranostic pairs with <sup>47</sup>Sc. Production of these isotopes through various nuclear reactions using either cyclotrons or linear accelerators is of particular interest and previous studies have provided results using accelerated beams of protons, deuterons, and alpha particles. A novel production technique, using an ion source cathode packed with natural calcium fluoride material and irradiated with a <sup>3</sup>He beam, was tested at the Nuclear Science Laboratory at the University of Notre Dame in order to initially study the production of <sup>41</sup>Ca. Gamma-ray spectrometry revealed presence of <sup>43</sup>Sc and <sup>44</sup>Sc in the target, and allowed for the first measurement of their yield due to reactions of <sup>3</sup>He on natural calcium. The calculated thick target yields of <sup>43</sup>Sc and <sup>44g</sup>Sc from the reactions <sup>nat</sup>Ca(<sup>3</sup>He,x)<sup>43</sup>Sc and <sup>nat</sup>Ca(<sup>3</sup>He,x)<sup>44g</sup>Sc are compared to theoretical results using TALYS cross section models. Overall, results agree well with models at lower beam energies but tend to diverge at higher energies.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"215 ","pages":"Article 111580"},"PeriodicalIF":1.6,"publicationDate":"2024-11-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142638198","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-31DOI: 10.1016/j.apradiso.2024.111579
Myung-Hwan Jung , Jun Kue Park , Sung-Chul Yang , Hye Min Jang , Kwon Soo Chun , Won-Je Cho , Sang Wook Kim
In this work the nuclear reaction routes 70Zn(p,x)64,67Cu, 66,67Ga, and 65,69mZn, induced by a high-energy proton beam up to 100 MeV have been investigated. Demand for 67Cu is increasing worldwide because it is known to be one of the best radionuclides having theranostic properties. Thus, efforts to improve its global production are underway. In previous studies, experimental data about nuclear cross-section measurements on 70Zn-enriched targets induced by proton beams were limited to an energy range of up to 70 MeV. Our goal was to extend nuclear data on 70Zn over a wider and unexplored so far region from 42 MeV to 98 MeV. As a result, our data turned out to be in good agreement with the literature ones in the overlapping energy range. In addition, to the best of our knowledge, new nuclear data exceeding 70 MeV were provided, demonstrating an excellent analytical method for producing 67Cu in the extended energy range.
{"title":"First 70Zn(p,x) nuclear cross section measurements for theranostic 67Cu radionuclide production extended up to 100 MeV","authors":"Myung-Hwan Jung , Jun Kue Park , Sung-Chul Yang , Hye Min Jang , Kwon Soo Chun , Won-Je Cho , Sang Wook Kim","doi":"10.1016/j.apradiso.2024.111579","DOIUrl":"10.1016/j.apradiso.2024.111579","url":null,"abstract":"<div><div>In this work the nuclear reaction routes <sup>70</sup>Zn(p,x)<sup>64,67</sup>Cu, <sup>66,67</sup>Ga, and <sup>65,69m</sup>Zn, induced by a high-energy proton beam up to 100 MeV have been investigated. Demand for <sup>67</sup>Cu is increasing worldwide because it is known to be one of the best radionuclides having theranostic properties. Thus, efforts to improve its global production are underway. In previous studies, experimental data about nuclear cross-section measurements on <sup>70</sup>Zn-enriched targets induced by proton beams were limited to an energy range of up to 70 MeV. Our goal was to extend nuclear data on <sup>70</sup>Zn over a wider and unexplored so far region from 42 MeV to 98 MeV. As a result, our data turned out to be in good agreement with the literature ones in the overlapping energy range. In addition, to the best of our knowledge, new nuclear data exceeding 70 MeV were provided, demonstrating an excellent analytical method for producing <sup>67</sup>Cu in the extended energy range.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"215 ","pages":"Article 111579"},"PeriodicalIF":1.6,"publicationDate":"2024-10-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142613772","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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