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}
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}
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.2026.112423
Warren Kilby , Chad Lee , Karen Morrison , Linnette Capo , Maki Ikeura , Michael Torgov , Tioga J. Martin , Maria-Christina Malinao , Dave Dewitt , Perry Young , Kendall Morrison , Arthur Raitano
Boronotyrosine (BTS) is a candidate boron delivery compound for Boron Neutron Capture Therapy (BNCT). In comparison to the current standard, boronophenylalanine (BPA), BTS provides higher solubility and improved specificity, retention, and tumor control in small animal models. The purpose of this work is to estimate the advantages of BTS for BNCT of human head and neck cancer.
Biodistributions of BTS and BPA were measured after bolus injection using a human hypopharyngeal cancer xenograft model in CB17 SCID mice. Pharmaco-kinetic (P-K) models were used to allow bolus response to be generalized to arbitrary infusion schedules. Allometric scaling was used to predict human biodistributions from these models. A treatment planning study of 11 head and neck cancer patients was performed to compare the BNCT dose distributions achievable using BTS and BPA.
The scaled P-K model boron concentration predictions for BPA were consistent with published measurements in human blood, tumor, and skin. Simulated infusions in a human patient gave mean tumor boron concentration during treatment of 57.2 ppm and 89.3 ppm for BPA and BTS, respectively. Tumor-to-blood and tumor-to-skin boron concentration ratios were 3.7:1 and 2.1:1 for BPA and 12.0:1 and 1.8:1 for BTS. GTV D95% increased from mean 29.5 Gy-Eq [26.4 Gy-Eq – 34.3 Gy-Eq] with BPA to 40.7 Gy-Eq [32.7 Gy-Eq – 58.3 Gy-Eq] with BTS for identical skin and mucosa dose constraints. BTS also demonstrated 10 %–40 % reduction in dose to parotid glands, spinal cord and non-specified normal tissue.
These results motivate further development and testing of BTS as a delivery compound for BNCT.
{"title":"First estimation of the clinical utility of boronotyrosine as a boron delivery compound for boron neutron capture therapy in head and neck cancer","authors":"Warren Kilby , Chad Lee , Karen Morrison , Linnette Capo , Maki Ikeura , Michael Torgov , Tioga J. Martin , Maria-Christina Malinao , Dave Dewitt , Perry Young , Kendall Morrison , Arthur Raitano","doi":"10.1016/j.apradiso.2026.112423","DOIUrl":"10.1016/j.apradiso.2026.112423","url":null,"abstract":"<div><div>Boronotyrosine (BTS) is a candidate boron delivery compound for Boron Neutron Capture Therapy (BNCT). In comparison to the current standard, boronophenylalanine (BPA), BTS provides higher solubility and improved specificity, retention, and tumor control in small animal models. The purpose of this work is to estimate the advantages of BTS for BNCT of human head and neck cancer.</div><div>Biodistributions of BTS and BPA were measured after bolus injection using a human hypopharyngeal cancer xenograft model in CB17 SCID mice. Pharmaco-kinetic (P-K) models were used to allow bolus response to be generalized to arbitrary infusion schedules. Allometric scaling was used to predict human biodistributions from these models. A treatment planning study of 11 head and neck cancer patients was performed to compare the BNCT dose distributions achievable using BTS and BPA.</div><div>The scaled P-K model boron concentration predictions for BPA were consistent with published measurements in human blood, tumor, and skin. Simulated infusions in a human patient gave mean tumor boron concentration during treatment of 57.2 ppm and 89.3 ppm for BPA and BTS, respectively. Tumor-to-blood and tumor-to-skin boron concentration ratios were 3.7:1 and 2.1:1 for BPA and 12.0:1 and 1.8:1 for BTS. GTV D95% increased from mean 29.5 Gy-Eq [26.4 Gy-Eq – 34.3 Gy-Eq] with BPA to 40.7 Gy-Eq [32.7 Gy-Eq – 58.3 Gy-Eq] with BTS for identical skin and mucosa dose constraints. BTS also demonstrated 10 %–40 % reduction in dose to parotid glands, spinal cord and non-specified normal tissue.</div><div>These results motivate further development and testing of BTS as a delivery compound for BNCT.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112423"},"PeriodicalIF":1.8,"publicationDate":"2026-01-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145920662","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.2026.112419
R. Rivas-Gómez , D. Romero-Fuentes , B. Quintana-Arnés , R. Carballeira
Precise radionuclide measurements are crucial for absolute dating in paleoclimatic studies. Mazinger, a very-low-level background and high-efficiency -ray spectrometer, was upgraded with two anti-muon veto detectors and its acquisition electronics have been reconfigured, both to improve detection limits and handle higher event rates coming from the veto system. The upgrade led to a doubling of Mazinger’s figure of merit and significantly reduce the background level. These improvements enhance Mazinger’s performance for geochronological applications. Application to 210Pb dating of a low-level activity sediment core from Sobrado Lagoon (Spain) produced an age model with uncertainties under 5%, matching correctly with the 137Cs profile.
{"title":"Towards the optimal performance of Mazinger, a shallow γ-ray spectrometry system of high efficiency and very-low-level background, devoted to 210Pb and U–Th dating for paleoclimatic applications","authors":"R. Rivas-Gómez , D. Romero-Fuentes , B. Quintana-Arnés , R. Carballeira","doi":"10.1016/j.apradiso.2026.112419","DOIUrl":"10.1016/j.apradiso.2026.112419","url":null,"abstract":"<div><div>Precise radionuclide measurements are crucial for absolute dating in paleoclimatic studies. Mazinger, a very-low-level background and high-efficiency <span><math><mi>γ</mi></math></span>-ray spectrometer, was upgraded with two anti-muon veto detectors and its acquisition electronics have been reconfigured, both to improve detection limits and handle higher event rates coming from the veto system. The upgrade led to a doubling of Mazinger’s figure of merit and significantly reduce the background level. These improvements enhance Mazinger’s performance for geochronological applications. Application to <sup>210</sup>Pb dating of a low-level activity sediment core from Sobrado Lagoon (Spain) produced an age model with uncertainties under 5%, matching correctly with the <sup>137</sup>Cs profile.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112419"},"PeriodicalIF":1.8,"publicationDate":"2026-01-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145920711","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.2026.112418
Donghye Heo , Myoungjung Kim , Byoungchul Kim , Kyoungbeom Lee , Minjune Yang , MinSeok Park , Jae Seok Kim , Minsu Cho , Seokwon Yoon
To enhance regional preparedness for radiological emergencies and improve the reliability of internal dose assessments, this study developed and validated tritium-spiked urine samples and low-level tritium reference materials. These materials were produced as part of a collaborative program within the Asia Dose Assessment Expert Network, aiming to standardize analytical methods for internal tritium exposure across Korea, China, and Japan. Urine samples were prepared by adding certified tritium reference material to a processed urine matrix, followed by rigorous evaluation of homogeneity and stability. Results from repeated measurements confirmed uniform distribution (maximum deviation within ±10 %) and minimal volatility over a three-month period. Analytical reliability was verified via blind testing using both direct and distillation measurement methods, with the root mean square error (RMSE) values of 5.06 % and 10.5 %, respectively.
In parallel, low-level tritium reference materials targeting 5 Bq/kg were produced through a six-step gravimetric dilution using a certified tritium stock solution. Homogeneity and activity concentration were assessed using one-way ANOVA and considering a quench correction with a low-level liquid scintillation counter. The standard uncertainty of detection efficiency was estimated at 1.5 % (68 % confidence level), and comparison with the internal standard method showed an efficiency bias of only 0.2 %.
The validated reference materials and quality evaluation protocols presented in this study provide a robust foundation for harmonizing tritium bioassay techniques in East Asia. These outcomes are expected to support future efforts in standardizing internal exposure assessment methods and establishing a regional cooperative monitoring framework.
{"title":"Development and validation of reference materials for tritium radioactivity analysis comparison programs","authors":"Donghye Heo , Myoungjung Kim , Byoungchul Kim , Kyoungbeom Lee , Minjune Yang , MinSeok Park , Jae Seok Kim , Minsu Cho , Seokwon Yoon","doi":"10.1016/j.apradiso.2026.112418","DOIUrl":"10.1016/j.apradiso.2026.112418","url":null,"abstract":"<div><div>To enhance regional preparedness for radiological emergencies and improve the reliability of internal dose assessments, this study developed and validated tritium-spiked urine samples and low-level tritium reference materials. These materials were produced as part of a collaborative program within the Asia Dose Assessment Expert Network, aiming to standardize analytical methods for internal tritium exposure across Korea, China, and Japan. Urine samples were prepared by adding certified tritium reference material to a processed urine matrix, followed by rigorous evaluation of homogeneity and stability. Results from repeated measurements confirmed uniform distribution (maximum deviation within ±10 %) and minimal volatility over a three-month period. Analytical reliability was verified via blind testing using both direct and distillation measurement methods, with the root mean square error (RMSE) values of 5.06 % and 10.5 %, respectively.</div><div>In parallel, low-level tritium reference materials targeting 5 Bq/kg were produced through a six-step gravimetric dilution using a certified tritium stock solution. Homogeneity and activity concentration were assessed using one-way ANOVA and considering a quench correction with a low-level liquid scintillation counter. The standard uncertainty of detection efficiency was estimated at 1.5 % (68 % confidence level), and comparison with the internal standard method showed an efficiency bias of only 0.2 %.</div><div>The validated reference materials and quality evaluation protocols presented in this study provide a robust foundation for harmonizing tritium bioassay techniques in East Asia. These outcomes are expected to support future efforts in standardizing internal exposure assessment methods and establishing a regional cooperative monitoring framework.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112418"},"PeriodicalIF":1.8,"publicationDate":"2026-01-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145964929","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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