Pub Date : 2026-01-10DOI: 10.1016/j.apradiso.2026.112436
D. Gurau , D. Stanga , O. Sima , L. Done
In this work a simple approach for estimating the true value of the computed full-energy peak (FEP) efficiency and the associated uncertainty is described. This approach makes use of a multiplicative model where the bias is expressed as a correction factor. It is based on the least squares estimation that provides estimates for the correction factor and the associated uncertainty for a future computation. Once calculated, these estimates can subsequently be used for estimating the true value of the computed FEP efficiency and the associated uncertainty for a future computation. The estimation method was applied to two datasets and the results show that codes such as GEANT4 and GESPECOR may provide values of the FEP efficiency that are very close to their true values.
{"title":"Evaluating the uncertainty associated with computed values of the full-energy peak efficiency used in gamma spectrometry measurements","authors":"D. Gurau , D. Stanga , O. Sima , L. Done","doi":"10.1016/j.apradiso.2026.112436","DOIUrl":"10.1016/j.apradiso.2026.112436","url":null,"abstract":"<div><div>In this work a simple approach for estimating the true value of the computed full-energy peak (FEP) efficiency and the associated uncertainty is described. This approach makes use of a multiplicative model where the bias is expressed as a correction factor. It is based on the least squares estimation that provides estimates for the correction factor and the associated uncertainty for a future computation. Once calculated, these estimates can subsequently be used for estimating the true value of the computed FEP efficiency and the associated uncertainty for a future computation. The estimation method was applied to two datasets and the results show that codes such as GEANT4 and GESPECOR may provide values of the FEP efficiency that are very close to their true values.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"230 ","pages":"Article 112436"},"PeriodicalIF":1.8,"publicationDate":"2026-01-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145976459","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}
<div><div>In the field of nuclear safety and environmental monitoring, accurate measurement of radionuclide activity in aerosols collected on filters is of critical importance, particularly in terms of the traceability of such measurements, as they can inform operational decision-making. Laboratories, especially in France, commonly employ radionuclides such as <span><math><mrow><msup><mrow></mrow><mrow><mn>137</mn></mrow></msup><mi>Cs</mi></mrow></math></span> for <span><math><mi>γ</mi></math></span>-ray or <span><math><mi>β</mi></math></span>-particle emitters, <span><math><mrow><msup><mrow></mrow><mrow><mn>90</mn></mrow></msup><mi>Sr</mi><msup><mrow><mo>/</mo></mrow><mrow><mn>90</mn></mrow></msup><mi>Y</mi></mrow></math></span> for pure <span><math><mi>β</mi></math></span>-particle emitters and <span><math><mrow><msup><mrow></mrow><mrow><mn>239</mn></mrow></msup><mi>Pu</mi></mrow></math></span> for <span><math><mi>α</mi></math></span>-particle emitters to calibrate their measurement instruments. However, the use of <span><math><mrow><msup><mrow></mrow><mrow><mn>239</mn></mrow></msup><mi>Pu</mi></mrow></math></span> presents challenges, including the necessity to destroy the filter to determine its traceable activity and associated uncertainties with liquid scintillation counting. <span><math><mrow><msup><mrow></mrow><mrow><mn>241</mn></mrow></msup><mi>Am</mi></mrow></math></span> is an alternative reference nuclide. It can be measured non-destructively while maintaining traceability to the International System (SI) and having properties similar to those of <span><math><mrow><msup><mrow></mrow><mrow><mn>239</mn></mrow></msup><mi>Pu</mi></mrow></math></span> in <span><math><mi>α</mi></math></span>-particle measurements. The ASNR’s ICARE<span><span><sup>1</sup></span></span> test bench, a unique facility in Europe, is utilized to produce reference filters with <span><math><mrow><msup><mrow></mrow><mrow><mn>241</mn></mrow></msup><mi>Am</mi></mrow></math></span> of a defined AMAD.<span><span><sup>2</sup></span></span> The reference activity of these filters is measured via <span><math><mi>γ</mi></math></span>-ray spectrometry on a CEA/LNHB reference HPGe<span><span><sup>3</sup></span></span> spectrometer. <span><math><mrow><msup><mrow></mrow><mrow><mn>241</mn></mrow></msup><mi>Am</mi></mrow></math></span> provides accurate activity determination with minimal uncertainty. The final calibration comparison on a gas-proportional counter with two PTFE<span><span><sup>4</sup></span></span> membrane filters, one with <span><math><mrow><msup><mrow></mrow><mrow><mn>239</mn></mrow></msup><mi>Pu</mi></mrow></math></span> the other with <span><math><mrow><msup><mrow></mrow><mrow><mn>241</mn></mrow></msup><mi>Am</mi></mrow></math></span>, confirm the advantages in using <span><math><mrow><msup><mrow></mrow><mrow><mn>241</mn></mrow></msup><mi>Am</mi></mrow></math></span> as nuclide for reference <span><math><mi>α</mi></math></span>-filters. The high quality of th
{"title":"241Am: A new nuclide for reference α−filter production and calibration","authors":"Grégoire Dougniaux , Benoît Sabot , Bernadette Dhieux Lestaevel , Sylvie Pierre","doi":"10.1016/j.apradiso.2026.112435","DOIUrl":"10.1016/j.apradiso.2026.112435","url":null,"abstract":"<div><div>In the field of nuclear safety and environmental monitoring, accurate measurement of radionuclide activity in aerosols collected on filters is of critical importance, particularly in terms of the traceability of such measurements, as they can inform operational decision-making. Laboratories, especially in France, commonly employ radionuclides such as <span><math><mrow><msup><mrow></mrow><mrow><mn>137</mn></mrow></msup><mi>Cs</mi></mrow></math></span> for <span><math><mi>γ</mi></math></span>-ray or <span><math><mi>β</mi></math></span>-particle emitters, <span><math><mrow><msup><mrow></mrow><mrow><mn>90</mn></mrow></msup><mi>Sr</mi><msup><mrow><mo>/</mo></mrow><mrow><mn>90</mn></mrow></msup><mi>Y</mi></mrow></math></span> for pure <span><math><mi>β</mi></math></span>-particle emitters and <span><math><mrow><msup><mrow></mrow><mrow><mn>239</mn></mrow></msup><mi>Pu</mi></mrow></math></span> for <span><math><mi>α</mi></math></span>-particle emitters to calibrate their measurement instruments. However, the use of <span><math><mrow><msup><mrow></mrow><mrow><mn>239</mn></mrow></msup><mi>Pu</mi></mrow></math></span> presents challenges, including the necessity to destroy the filter to determine its traceable activity and associated uncertainties with liquid scintillation counting. <span><math><mrow><msup><mrow></mrow><mrow><mn>241</mn></mrow></msup><mi>Am</mi></mrow></math></span> is an alternative reference nuclide. It can be measured non-destructively while maintaining traceability to the International System (SI) and having properties similar to those of <span><math><mrow><msup><mrow></mrow><mrow><mn>239</mn></mrow></msup><mi>Pu</mi></mrow></math></span> in <span><math><mi>α</mi></math></span>-particle measurements. The ASNR’s ICARE<span><span><sup>1</sup></span></span> test bench, a unique facility in Europe, is utilized to produce reference filters with <span><math><mrow><msup><mrow></mrow><mrow><mn>241</mn></mrow></msup><mi>Am</mi></mrow></math></span> of a defined AMAD.<span><span><sup>2</sup></span></span> The reference activity of these filters is measured via <span><math><mi>γ</mi></math></span>-ray spectrometry on a CEA/LNHB reference HPGe<span><span><sup>3</sup></span></span> spectrometer. <span><math><mrow><msup><mrow></mrow><mrow><mn>241</mn></mrow></msup><mi>Am</mi></mrow></math></span> provides accurate activity determination with minimal uncertainty. The final calibration comparison on a gas-proportional counter with two PTFE<span><span><sup>4</sup></span></span> membrane filters, one with <span><math><mrow><msup><mrow></mrow><mrow><mn>239</mn></mrow></msup><mi>Pu</mi></mrow></math></span> the other with <span><math><mrow><msup><mrow></mrow><mrow><mn>241</mn></mrow></msup><mi>Am</mi></mrow></math></span>, confirm the advantages in using <span><math><mrow><msup><mrow></mrow><mrow><mn>241</mn></mrow></msup><mi>Am</mi></mrow></math></span> as nuclide for reference <span><math><mi>α</mi></math></span>-filters. The high quality of th","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"230 ","pages":"Article 112435"},"PeriodicalIF":1.8,"publicationDate":"2026-01-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146036117","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}
The Ionizing Radiation Metrology Laboratory (LMRI) from IFIN-HH has evaluated nuclear track detector responses to radon (222Rn). In order to perform the evaluation, a radon source was prepared using the standard system for the radon extraction from a solid 226Ra Pylon source with certified activity traceable to the NIST, USA. The solid state nuclear track detectors (SSNTDs) type TASTRACK PADC from TASL were exposed to radon in the radon chamber at the LMRI (1 m3 volume) together with the AlphaGuard DF2000 (AG) radon reference monitor. After exposure, the SSNTDs were placed and processed in a Clifton Digital bath with NaOH solution. After etching, an optical system (TASLImage) was used to determine the integrated exposure. The present analysis was made in order to develop a working procedure for the calibration of an SSNTD in a radon chamber. LMRI aims to extend the calibration services for customers with the nuclear track detectors calibration. The results for the radon activity concentration in air obtained with the SSNTDs were in good agreement (±10 %) with the values registered by the reference radon monitor.
{"title":"Nuclear track detectors evaluation for radon activity concentration measurements","authors":"Ioana Lalau , Aurelian Luca , Mastaneh Zadehrafi , Mihail-Razvan Ioan","doi":"10.1016/j.apradiso.2026.112421","DOIUrl":"10.1016/j.apradiso.2026.112421","url":null,"abstract":"<div><div>The Ionizing Radiation Metrology Laboratory (LMRI) from IFIN-HH has evaluated nuclear track detector responses to radon (<sup>222</sup>Rn). In order to perform the evaluation, a radon source was prepared using the standard system for the radon extraction from a solid <sup>226</sup>Ra Pylon source with certified activity traceable to the NIST, USA. The solid state nuclear track detectors (SSNTDs) type TASTRACK PADC from TASL were exposed to radon in the radon chamber at the LMRI (1 m<sup>3</sup> volume) together with the AlphaGuard DF2000 (AG) radon reference monitor. After exposure, the SSNTDs were placed and processed in a Clifton Digital bath with NaOH solution. After etching, an optical system (TASLImage) was used to determine the integrated exposure. The present analysis was made in order to develop a working procedure for the calibration of an SSNTD in a radon chamber. LMRI aims to extend the calibration services for customers with the nuclear track detectors calibration. The results for the radon activity concentration in air obtained with the SSNTDs were in good agreement (±10 %) with the values registered by the reference radon monitor.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112421"},"PeriodicalIF":1.8,"publicationDate":"2026-01-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145920714","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}
We evaluated charged particle and neutron environments in space modules constructed from various structural materials using Monte Carlo simulations. Error rates due to single event upsets (SEU) in silicon devices were also assessed. Charged particle environments in modules constructed from organic composite materials closely resemble those in conventional aluminum structures, whereas neutron environments showed notable differences. Compared to aluminum, organic composites reduced SEU rates by up to 55 %. Under a human habitat assumption with an additional water structure, thermal neutrons below 100 meV contribute approximately 10 % of the SEU rates through the 10B(n, α) reaction. This contribution from thermal neutrons could be effectively eliminated using a 100-μm-thick thermal neutron absorption coating enriched with Gd2O3. These results suggest that organic composite materials, in combination with thermal neutron absorption paint, offer potential advantages for radiation safety in space by protecting both humans and electronic devices.
{"title":"Shielding design to mitigate neutron-induced single event upsets in space","authors":"Masayuki Naito , Shusaku Mandai , Norihito Sakai , Koudai Ueda , Hiromasa Tanahashi , Satoshi Kodaira","doi":"10.1016/j.apradiso.2026.112430","DOIUrl":"10.1016/j.apradiso.2026.112430","url":null,"abstract":"<div><div>We evaluated charged particle and neutron environments in space modules constructed from various structural materials using Monte Carlo simulations. Error rates due to single event upsets (SEU) in silicon devices were also assessed. Charged particle environments in modules constructed from organic composite materials closely resemble those in conventional aluminum structures, whereas neutron environments showed notable differences. Compared to aluminum, organic composites reduced SEU rates by up to 55 %. Under a human habitat assumption with an additional water structure, thermal neutrons below 100 meV contribute approximately 10 % of the SEU rates through the <sup>10</sup>B(n, α) reaction. This contribution from thermal neutrons could be effectively eliminated using a 100-μm-thick thermal neutron absorption coating enriched with Gd<sub>2</sub>O<sub>3</sub>. These results suggest that organic composite materials, in combination with thermal neutron absorption paint, offer potential advantages for radiation safety in space by protecting both humans and electronic devices.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112430"},"PeriodicalIF":1.8,"publicationDate":"2026-01-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145920660","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 : 2026-01-08DOI: 10.1016/j.apradiso.2026.112426
Berna Oto , Esra Kavaz , Nurtaç Çakar , Halime Erzen Yıldız , Hamza Tunç
This study investigates the effects of doping HfO2 (hafnium oxide) on Al2Si2O5(OH)4–KAlSi3O8–SiO2 ceramics, fabricated via conventional firing and sintering, for photon and neutron shielding applications. Experimental measurements were performed using a133Ba source for gamma shielding and a241Am/Be neutron source for neutron shielding. At 81 keV gamma energy, the radiation attenuation properties of Hf0 (undoped) and Hf5 (doped, containing 30 % HfO2) ceramics showed an increase in the mass attenuation coefficient from 0.180 to 1.812 cm2/g and in the linear attenuation coefficient from 0.417 to 5.799 cm−1, while the mean free path (mfp) decreased from 2.398 to 0.172 cm, indicating a clear compositional dependence. Theoretical calculations were carried out using the EpiXS program. Among the produced ceramics, the Hf5 sample exhibited the highest neutron absorption rate, reaching 59.31 %. This work presents an innovative approach for developing HfO2-doped ceramics for radiation-shielding applications. Compared to undoped systems, the incorporation of HfO2 significantly enhances both gamma- and neutron-attenuation capabilities. The results demonstrate that HfO2-doped ceramics constitute sustainable, cost-effective, and efficient alternatives for radiation protection in nuclear facilities, medical imaging technologies, and space applications.
{"title":"Design, structural evolution, and radiation attenuation behavior of HfO2-Modified ceramics","authors":"Berna Oto , Esra Kavaz , Nurtaç Çakar , Halime Erzen Yıldız , Hamza Tunç","doi":"10.1016/j.apradiso.2026.112426","DOIUrl":"10.1016/j.apradiso.2026.112426","url":null,"abstract":"<div><div>This study investigates the effects of doping HfO<sub>2</sub> (hafnium oxide) on Al<sub>2</sub>Si<sub>2</sub>O<sub>5</sub>(OH)<sub>4</sub>–KAlSi<sub>3</sub>O<sub>8</sub>–SiO<sub>2</sub> ceramics, fabricated via conventional firing and sintering, for photon and neutron shielding applications. Experimental measurements were performed using a<sup>133</sup>Ba source for gamma shielding and a<sup>241</sup>Am/Be neutron source for neutron shielding. At 81 keV gamma energy, the radiation attenuation properties of Hf0 (undoped) and Hf5 (doped, containing 30 % HfO<sub>2</sub>) ceramics showed an increase in the mass attenuation coefficient from 0.180 to 1.812 cm<sup>2</sup>/g and in the linear attenuation coefficient from 0.417 to 5.799 cm<sup>−1</sup>, while the mean free path (mfp) decreased from 2.398 to 0.172 cm, indicating a clear compositional dependence. Theoretical calculations were carried out using the EpiXS program. Among the produced ceramics, the Hf5 sample exhibited the highest neutron absorption rate, reaching 59.31 %. This work presents an innovative approach for developing HfO<sub>2</sub>-doped ceramics for radiation-shielding applications. Compared to undoped systems, the incorporation of HfO<sub>2</sub> significantly enhances both gamma- and neutron-attenuation capabilities. The results demonstrate that HfO<sub>2</sub>-doped ceramics constitute sustainable, cost-effective, and efficient alternatives for radiation protection in nuclear facilities, medical imaging technologies, and space applications.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112426"},"PeriodicalIF":1.8,"publicationDate":"2026-01-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145920716","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 : 2026-01-07DOI: 10.1016/j.apradiso.2026.112424
R. Adibi , M. Zahedifar , E. Sadeghi , S. Harooni
In response to the growing demand for sustainable and cost-effective dosimetric materials, this study explores the synthesis and thermoluminescence (TL) characteristics of calcium oxide (CaO) particles obtained from chicken eggshell biowaste. CaO was prepared through a green calcination route at 1000 °C and its structural and morphological properties were confirmed via XRD, SEM, EDX, and elemental mapping, indicating high-purity nanocrystalline CaO with uniform elemental distribution. The TL response of the synthesized CaO was evaluated under gamma irradiation with systematic optimization of annealing conditions. TL glow curve exhibited two broad glow peaks centered at about 145 and 273 °C. Samples annealed at 500 °C for 20 min exhibited the highest TL sensitivity. Three component glow peaks were identified in the complex glow curve of the synthesized sample. Among these, the high temperature peak centered at 273 °C with the activation energy of 1.13 eV was revealed as the most relevant for dosimetric applications due to its thermal stability and strong TL emission. The synthesized CaO showed a broad linear dose-response ranging from 5 to 500 Gy with excellent correlation (R2 ≈ 0.99), minimal fading of ∼8 % over 35 days for the high-temperature peak and stability over multiple annealing, irradiation and readout cycles. These findings underscore the potential of eggshell-derived CaO as a low-cost, eco-friendly, and reliable TL dosimeter for high-dose radiation monitoring.
{"title":"Thermoluminescent dosimetry properties of calcium oxide obtained from eggshells","authors":"R. Adibi , M. Zahedifar , E. Sadeghi , S. Harooni","doi":"10.1016/j.apradiso.2026.112424","DOIUrl":"10.1016/j.apradiso.2026.112424","url":null,"abstract":"<div><div>In response to the growing demand for sustainable and cost-effective dosimetric materials, this study explores the synthesis and thermoluminescence (TL) characteristics of calcium oxide (CaO) particles obtained from chicken eggshell biowaste. CaO was prepared through a green calcination route at 1000 °C and its structural and morphological properties were confirmed via XRD, SEM, EDX, and elemental mapping, indicating high-purity nanocrystalline CaO with uniform elemental distribution. The TL response of the synthesized CaO was evaluated under gamma irradiation with systematic optimization of annealing conditions. TL glow curve exhibited two broad glow peaks centered at about 145 and 273 °C. Samples annealed at 500 °C for 20 min exhibited the highest TL sensitivity. Three component glow peaks were identified in the complex glow curve of the synthesized sample. Among these, the high temperature peak centered at 273 °C with the activation energy of 1.13 eV was revealed as the most relevant for dosimetric applications due to its thermal stability and strong TL emission. The synthesized CaO showed a broad linear dose-response ranging from 5 to 500 Gy with excellent correlation (R<sup>2</sup> ≈ 0.99), minimal fading of ∼8 % over 35 days for the high-temperature peak and stability over multiple annealing, irradiation and readout cycles. These findings underscore the potential of eggshell-derived CaO as a low-cost, eco-friendly, and reliable TL dosimeter for high-dose radiation monitoring.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112424"},"PeriodicalIF":1.8,"publicationDate":"2026-01-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145920663","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 : 2026-01-07DOI: 10.1016/j.apradiso.2026.112425
H.A. Abo-Mosallam , Mohamed I. Farouk , Mostafa I. Abdelglil , A.G. Darwish
The primary objective of this work is to develop eco-friendly and cost-effective glasses for radiation shielding. The phosphosilicate non-crystalline materials were prepared based on the 30CaO-(20-X)MgO-XTiO2-5P2O5-45SiO2 glass system (where X = 0, 1.0, 2.0, 4.0, and 6.0 mol%). The effect of adding various TiO2 contents on physical properties, optical power, and radiation mitigation efficiency was studied. XRD examination established the vitreous nature of all investigated samples. The results showed that the density, oxygen packing density, and field strength improved with increased TiO2 content up to 6.0 mol %, attributed to tightening of the glass network strength. The UV–visible spectra show nearly overlapping absorbance spectra with a steep absorption edge around 350–400 nm, strong UV absorption, and high transparency through the visible–NIR. The evaluation of the neutron shielding performance was carried out using Phy-X/PSD for photon energies between 0.015 and 15 MeV. Radiation defense parameters, including linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), half-value layer (HVL), mean free path (MFP), tenth value layer (TVL), and effective atomic number (Zeff), were calculated. Radiation parameters demonstrate that the addition of titanium dioxide significantly improves the performance of phospho-silicate glass in mitigating gamma radiation. The results indicate that the prepared glass has great potential as an effective, inexpensive, and environmentally friendly material for radiation mitigation applications, compared to some existing shielding materials and glass systems.
{"title":"Design and characterization of eco-friendly phospho-silicate glasses modified with TiO2 in the CaO-MgO-P2O5-SiO2 system for radiation shielding protection","authors":"H.A. Abo-Mosallam , Mohamed I. Farouk , Mostafa I. Abdelglil , A.G. Darwish","doi":"10.1016/j.apradiso.2026.112425","DOIUrl":"10.1016/j.apradiso.2026.112425","url":null,"abstract":"<div><div>The primary objective of this work is to develop eco-friendly and cost-effective glasses for radiation shielding. The phosphosilicate non-crystalline materials were prepared based on the 30CaO-(20-X)MgO-XTiO<sub>2</sub>-5P<sub>2</sub>O<sub>5</sub>-45SiO<sub>2</sub> glass system (where X = 0, 1.0, 2.0, 4.0, and 6.0 mol%). The effect of adding various TiO<sub>2</sub> contents on physical properties, optical power, and radiation mitigation efficiency was studied. XRD examination established the vitreous nature of all investigated samples. The results showed that the density, oxygen packing density, and field strength improved with increased TiO<sub>2</sub> content up to 6.0 mol %, attributed to tightening of the glass network strength. The UV–visible spectra show nearly overlapping absorbance spectra with a steep absorption edge around 350–400 nm, strong UV absorption, and high transparency through the visible–NIR. The evaluation of the neutron shielding performance was carried out using Phy-X/PSD for photon energies between 0.015 and 15 MeV. Radiation defense parameters, including linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), half-value layer (HVL), mean free path (MFP), tenth value layer (TVL), and effective atomic number (Zeff), were calculated. Radiation parameters demonstrate that the addition of titanium dioxide significantly improves the performance of phospho-silicate glass in mitigating gamma radiation. The results indicate that the prepared glass has great potential as an effective, inexpensive, and environmentally friendly material for radiation mitigation applications, compared to some existing shielding materials and glass systems.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112425"},"PeriodicalIF":1.8,"publicationDate":"2026-01-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145920659","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 : 2026-01-07DOI: 10.1016/j.apradiso.2026.112422
K.A. Chipps , S.D. Pain , C. Matei , H.I Garland , M.M. Grinder , T.T. King , B. Sudarsan , E. Torres
As part of a broader campaign to understand gamma-induced charged particle emission with multiple materials, the cross sections of the (, p), and (, ) reactions on a natural zinc target were measured. These cross sections were measured experimentally using a kinematically-complete, event-by-event methodology, using monoenergetic gamma ray beams from the High Intensity Gamma Source (HIS) facility, ranging from 10 to 19 MeV, to bombard a natural metallic zinc target in vacuum. The measured cross sections are compared with theoretical predictions using the statistical model approach, which is important for the use of such models in real-world applications such as the production of the 67Cu theranostic via the 68Zn(, p) reaction.
{"title":"Measurement of gamma-induced reactions between 10 and 19 MeV on natural zinc with potential application to 67Cu production","authors":"K.A. Chipps , S.D. Pain , C. Matei , H.I Garland , M.M. Grinder , T.T. King , B. Sudarsan , E. Torres","doi":"10.1016/j.apradiso.2026.112422","DOIUrl":"10.1016/j.apradiso.2026.112422","url":null,"abstract":"<div><div>As part of a broader campaign to understand gamma-induced charged particle emission with multiple materials, the cross sections of the (<span><math><mi>γ</mi></math></span>, p), and (<span><math><mi>γ</mi></math></span>, <span><math><mi>α</mi></math></span>) reactions on a natural zinc target were measured. These cross sections were measured experimentally using a kinematically-complete, event-by-event methodology, using monoenergetic gamma ray beams from the High Intensity Gamma Source (HI<span><math><mi>γ</mi></math></span>S) facility, ranging from 10 to 19 MeV, to bombard a natural metallic zinc target in vacuum. The measured cross sections are compared with theoretical predictions using the statistical model approach, which is important for the use of such models in real-world applications such as the production of the <sup>67</sup>Cu theranostic via the <sup>68</sup>Zn(<span><math><mi>γ</mi></math></span>, p) reaction.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112422"},"PeriodicalIF":1.8,"publicationDate":"2026-01-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145920713","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}
Three borate-based glass samples with compositions of xBaO-15Na2O-10Al2O3-(70–2x)B2O3-(x+5)CaO (x = 5, 10, and 15 mol%) were fabricated through the melt-quenching route for the assessment of their structure, optical features, and radiation shielding efficiency. FTIR spectra revealed the coexistence of BO3 and BO4 structural units, whose relative proportions varied with increasing BaO and CaO content. Increasing the BaO and CaO fractions led to a redshift in the UV–Visible spectra, reflecting a higher degree of structural distortion in the borate glass framework. Both direct and indirect optical band gaps showed a decreasing trend (3.804 ± 0.01 to 3.028 ± 0.01 eV and 3.387 ± 0.01 to 2.807 ± 0.01 eV, respectively), attributed to the increased presence of non-bridging oxygens. The observed rise in Urbach energy (0.241 ± 0.001 to 0.346 ± 0.001 eV) suggests an increase in defect concentration and network disorder. Radiation shielding performance was assessed across 0.015–15 MeV, revealing that the linear attenuation coefficient (LAC) decreased with photon energy but increased with BaO content, reaching 67.034 cm−1 at 0.015 MeV for the Ba15Ca20 sample. The effective atomic number (Zeff) varied with energy and composition, attaining maximum values of 23.52, 29.98, and 33.88 for Ba5Ca10, Ba10Ca15, and Ba15Ca20 glasses, respectively, at 0.015 MeV. The half-value layer (HVL) values of the prepared glasses were consistently lower than those of previously reported BaO-SiO2-B2O3 systems, confirming superior attenuation efficiency. The results show that the developed glass system demonstrates excellent potential for multifunctional optical and radiation shielding purposes, such as medical radiation shields, nuclear waste containment materials, and transparent shielding windows in nuclear facilities.
{"title":"Evaluation of the effect of adding BaO and CaO for gamma shielding and optical properties of borate glasses","authors":"M.I. Sayyed , Yasser Maghrbi , Aljawhara H. Almuqrin , Shrikant Biradar , Siti Nurasiah Mat Nawi , Mayeen Uddin Khandaker","doi":"10.1016/j.apradiso.2025.112410","DOIUrl":"10.1016/j.apradiso.2025.112410","url":null,"abstract":"<div><div>Three borate-based glass samples with compositions of xBaO-15Na<sub>2</sub>O-10Al<sub>2</sub>O<sub>3</sub>-(70–2x)B<sub>2</sub>O<sub>3</sub>-(x+5)CaO (x = 5, 10, and 15 mol%) were fabricated through the melt-quenching route for the assessment of their structure, optical features, and radiation shielding efficiency. FTIR spectra revealed the coexistence of BO<sub>3</sub> and BO<sub>4</sub> structural units, whose relative proportions varied with increasing BaO and CaO content. Increasing the BaO and CaO fractions led to a redshift in the UV–Visible spectra, reflecting a higher degree of structural distortion in the borate glass framework. Both direct and indirect optical band gaps showed a decreasing trend (3.804 ± 0.01 to 3.028 ± 0.01 eV and 3.387 ± 0.01 to 2.807 ± 0.01 eV, respectively), attributed to the increased presence of non-bridging oxygens. The observed rise in Urbach energy (0.241 ± 0.001 to 0.346 ± 0.001 eV) suggests an increase in defect concentration and network disorder. Radiation shielding performance was assessed across 0.015–15 MeV, revealing that the linear attenuation coefficient (LAC) decreased with photon energy but increased with BaO content, reaching 67.034 cm<sup>−1</sup> at 0.015 MeV for the Ba15Ca20 sample. The effective atomic number (Z<sub>eff</sub>) varied with energy and composition, attaining maximum values of 23.52, 29.98, and 33.88 for Ba5Ca10, Ba10Ca15, and Ba15Ca20 glasses, respectively, at 0.015 MeV. The half-value layer (HVL) values of the prepared glasses were consistently lower than those of previously reported BaO-SiO<sub>2</sub>-B<sub>2</sub>O<sub>3</sub> systems, confirming superior attenuation efficiency. The results show that the developed glass system demonstrates excellent potential for multifunctional optical and radiation shielding purposes, such as medical radiation shields, nuclear waste containment materials, and transparent shielding windows in nuclear facilities.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112410"},"PeriodicalIF":1.8,"publicationDate":"2026-01-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145916687","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 : 2026-01-06DOI: 10.1016/j.apradiso.2026.112420
N. Lisowska, J. Marganiec-Gałązka, M. Czudek, A. Kamiński, E. Kołakowska, E. Lech, A. Listkowska, D. Pawlak, P. Saganowski, Z. Tymiński
Terbium-161 is widely researched as a candidate for applications in nuclear medicine, creating an urgent need for precise activity determinations and accurate nuclear data. In this work, the activity of Tb-161 was measured using three LSC methods - 4πβ-γ-coincidence counting, TDCR and CIEMAT-NIST, giving consistent results. The half-life of the radionuclide was determined in a measurement campaign performed over approximately 42 days using two TDCR systems. The obtained result of 6.9618(18) days validates the recently reported values in literature data and confirms that the half-life of Tb-161 is higher than the currently recommended value of 6.89(2) days (Reich, 2011).
{"title":"Activity standardization and determination of the half-life of Tb-161","authors":"N. Lisowska, J. Marganiec-Gałązka, M. Czudek, A. Kamiński, E. Kołakowska, E. Lech, A. Listkowska, D. Pawlak, P. Saganowski, Z. Tymiński","doi":"10.1016/j.apradiso.2026.112420","DOIUrl":"10.1016/j.apradiso.2026.112420","url":null,"abstract":"<div><div>Terbium-161 is widely researched as a candidate for applications in nuclear medicine, creating an urgent need for precise activity determinations and accurate nuclear data. In this work, the activity of Tb-161 was measured using three LSC methods - 4πβ-γ-coincidence counting, TDCR and CIEMAT-NIST, giving consistent results. The half-life of the radionuclide was determined in a measurement campaign performed over approximately 42 days using two TDCR systems. The obtained result of 6.9618(18) days validates the recently reported values in literature data and confirms that the half-life of Tb-161 is higher than the currently recommended value of 6.89(2) days (Reich, 2011).</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112420"},"PeriodicalIF":1.8,"publicationDate":"2026-01-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145920718","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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