Pub Date : 2025-12-19DOI: 10.1016/j.apradiso.2025.112392
Miho Otaki , Markus Nyman , Kerttuli Helariutta , Risto Koivula
The phosphonate-functionalized hybrid sorbent SG85-TTHMP was evaluated for its potential in the selective recovery of 169Yb from irradiated Tm2O3 targets, with a focus on improving separation efficiency using complexing agents and tailored elution strategies. Batch experiments conducted under equimolar conditions of Tm3+ and Yb3+ at pH 3 yielded a modest Yb/Tm separation factor of 2.1–2.3. Post-loading elution with complexing agents facilitated the removal of excess Tm3+, and subsequent nitric acid stripping produced a more Yb-enriched solution fraction. This enrichment was further confirmed through fixed-bed column experiments with a solution derived from irradiated Tm2O3 targets of 169Tm(p,n)169Yb reaction, employing a loading–elution–stripping sequence that consistently yielded 169Yb-enriched fractions. Tailored elution prior to acid stripping proved effective in enhancing overall enrichment performance. Combined with SG85-TTHMP's operational simplicity and environmental compatibility, these results support its potential utility in selective lanthanide separation for radiochemical applications.
{"title":"Selective separation of 169Yb from proton-irradiated Tm2O3 targets using phosphonate-functionalized hybrid sorbents","authors":"Miho Otaki , Markus Nyman , Kerttuli Helariutta , Risto Koivula","doi":"10.1016/j.apradiso.2025.112392","DOIUrl":"10.1016/j.apradiso.2025.112392","url":null,"abstract":"<div><div>The phosphonate-functionalized hybrid sorbent SG85-TTHMP was evaluated for its potential in the selective recovery of <sup>169</sup>Yb from irradiated Tm<sub>2</sub>O<sub>3</sub> targets, with a focus on improving separation efficiency using complexing agents and tailored elution strategies. Batch experiments conducted under equimolar conditions of Tm<sup>3+</sup> and Yb<sup>3+</sup> at pH 3 yielded a modest Yb/Tm separation factor of 2.1–2.3. Post-loading elution with complexing agents facilitated the removal of excess Tm<sup>3+</sup>, and subsequent nitric acid stripping produced a more Yb-enriched solution fraction. This enrichment was further confirmed through fixed-bed column experiments with a solution derived from irradiated Tm<sub>2</sub>O<sub>3</sub> targets of <sup>169</sup>Tm(p,n)<sup>169</sup>Yb reaction, employing a loading–elution–stripping sequence that consistently yielded <sup>169</sup>Yb-enriched fractions. Tailored elution prior to acid stripping proved effective in enhancing overall enrichment performance. Combined with SG85-TTHMP's operational simplicity and environmental compatibility, these results support its potential utility in selective lanthanide separation for radiochemical applications.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112392"},"PeriodicalIF":1.8,"publicationDate":"2025-12-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145832572","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 : 2025-12-19DOI: 10.1016/j.apradiso.2025.112386
L. Quattrocchi , B. Gnoffo , E.V. Pagano , F. Risitano , M. Trimarchi , G. Cardella , A. Castoldi , E. De Filippo , E. Geraci , C. Guazzoni , G. Lanzalone , C. Maiolino , N.S. Martorana , A. Pagano , S. Pirrone , G. Politi , F. Rizzo , P. Russotto , G. Santagati , C. Zagami
The simultaneous detection of neutrons and charged particles is an important goal for the present and future facilities delivering radioactive ion beams (RIBs), especially in the case of neutron-rich ones, to understand structure and dynamics of reactions between systems with high isospin asymmetry. The NArCoS project (Neutron Array for Correlation Studies) is aimed at studying and developing a new modular and versatile array devoted to detecting, at the same time, neutrons and charged particles both with high energy and angular resolution. Final detector prototype will be an array of 64 elementary cells of EJ-276G plastic scintillators, with a dimension of 3×3×3 cm3, individually read by a SiPM matrix. One of the main points of the present work is to evaluate cross-talk phenomena in different conditions. In this contribution the results about cross-talk probability and neutron detection efficiency, obtained using two different Monte Carlo simulation codes, GEANT4 and MCNPX, will be discussed. All these studies will allow to evaluate the better setup for NArCoS array in order to maximize neutrons detection efficiency and to minimize the cross-talk probability.
{"title":"Study of neutron efficiency and cross-talk effects through Monte Carlo simulations for a new neutron detector NArCoS","authors":"L. Quattrocchi , B. Gnoffo , E.V. Pagano , F. Risitano , M. Trimarchi , G. Cardella , A. Castoldi , E. De Filippo , E. Geraci , C. Guazzoni , G. Lanzalone , C. Maiolino , N.S. Martorana , A. Pagano , S. Pirrone , G. Politi , F. Rizzo , P. Russotto , G. Santagati , C. Zagami","doi":"10.1016/j.apradiso.2025.112386","DOIUrl":"10.1016/j.apradiso.2025.112386","url":null,"abstract":"<div><div>The simultaneous detection of neutrons and charged particles is an important goal for the present and future facilities delivering radioactive ion beams (RIBs), especially in the case of neutron-rich ones, to understand structure and dynamics of reactions between systems with high isospin asymmetry. The NArCoS project (Neutron Array for Correlation Studies) is aimed at studying and developing a new modular and versatile array devoted to detecting, at the same time, neutrons and charged particles both with high energy and angular resolution. Final detector prototype will be an array of 64 elementary cells of EJ-276G plastic scintillators, with a dimension of 3×3×3 cm<sup>3</sup>, individually read by a SiPM matrix. One of the main points of the present work is to evaluate cross-talk phenomena in different conditions. In this contribution the results about cross-talk probability and neutron detection efficiency, obtained using two different Monte Carlo simulation codes, GEANT4 and MCNPX, will be discussed. All these studies will allow to evaluate the better setup for NArCoS array in order to maximize neutrons detection efficiency and to minimize the cross-talk probability.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112386"},"PeriodicalIF":1.8,"publicationDate":"2025-12-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145909766","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}
Precise measurements of atomic concentration and activity were performed in the same sample to determine the half-life of 107Pd. A pure 107Pd-containing solution was obtained after the dissolution and chemical purification of concretions formed in the equipment of a reprocessing plant. The concentration of 107Pd in the solution was measured by Multi-Collector Inductively Coupled Plasma Mass Spectrometry (MC-ICP-MS), associated with the isotope dilution technique. The activity of the solution was determined by Liquid Scintillation Counting (LSC) using both, the Triple to Double Coincidence Ratio (TDCR) and CIEMAT/NIST methods. These combined measurements resulted in a half-life of T1/2 = (5.94 ± 0.07) × 106 years with a coverage factor k of 1. The precision of the present measurement was improved by a factor of 2.5 in comparison to previous data.
{"title":"Determination of the 107Pd half-life","authors":"Marina Faure , Majd Shmeit , Karsten Kossert , Hélène Isnard , Céline Gautier","doi":"10.1016/j.apradiso.2025.112382","DOIUrl":"10.1016/j.apradiso.2025.112382","url":null,"abstract":"<div><div>Precise measurements of atomic concentration and activity were performed in the same sample to determine the half-life of <sup>107</sup>Pd. A pure <sup>107</sup>Pd-containing solution was obtained after the dissolution and chemical purification of concretions formed in the equipment of a reprocessing plant. The concentration of <sup>107</sup>Pd in the solution was measured by Multi-Collector Inductively Coupled Plasma Mass Spectrometry (MC-ICP-MS), associated with the isotope dilution technique. The activity of the solution was determined by Liquid Scintillation Counting (LSC) using both, the Triple to Double Coincidence Ratio (TDCR) and CIEMAT/NIST methods. These combined measurements resulted in a half-life of <em>T</em><sub>1/2</sub> = (5.94 ± 0.07) × 10<sup>6</sup> years with a coverage factor <em>k</em> of 1. The precision of the present measurement was improved by a factor of 2.5 in comparison to previous data.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112382"},"PeriodicalIF":1.8,"publicationDate":"2025-12-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145817436","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 : 2025-12-18DOI: 10.1016/j.apradiso.2025.112383
Yasser B. Saddeek , G. Abd elfadeel , M.A. Albedah , A.A. Showahy
Environmentally friendly lead-free CeO2-Al2O3-CuO borosilicate glasses were investigated by focusing on the Ce K-edge to enhance low-energy gamma-ray attenuation (15–60 keV). Five glass compositions with the nominal formula 60 B2O3 – 5 Al2O3 – 5 CeO2 - (30-x) SiO2 – x CuO (20 ≤ x ≤ 30 mol%) were synthesised via the melt-quenching method, and their structure was analysed via FTIR and SEM techniques. The mechanical properties were computed using the bond-compression and Makishima-Mackenzie models. Radiation shielding parameters (MAC, LAC, HVL, TVL, Zeff, Neff) were calculated using Phy-X/PSD over the energy range 0.015–15 MeV. XRD results revealed the amorphous nature of the prepared samples, while FTIR showed a transition from BO4 to BO3 units as CuO content increased. Density increment from 3.628 to 4.006 g/cm3, and Young's modulus increased from 29.7 (bond-compression model) to 56.4 (Makishima-Mackenzie model) GPa. The mass attenuation coefficient ranged from 25.32 cm2/g at 15 keV (30 mol% CuO) to 0.02 cm2/g at 15 MeV. The Ce K-edge at 40.4 keV significantly improved radiation blocking in the 40–60 keV diagnostic range, achieving over 99 % protection below 60 keV. A comparison with literature data reveals that the investigated glasses are non-toxic and suitable than lead- and bismuth-based shields in the diagnostic X-ray range, where the Ce K-edge effect offers notable benefits.
{"title":"Radiation shielding and structural characteristics of CeO2-CuO borosilicate glasses: Role of Ce K-edge in low-energy gamma−attenuation","authors":"Yasser B. Saddeek , G. Abd elfadeel , M.A. Albedah , A.A. Showahy","doi":"10.1016/j.apradiso.2025.112383","DOIUrl":"10.1016/j.apradiso.2025.112383","url":null,"abstract":"<div><div>Environmentally friendly lead-free CeO<sub>2</sub>-Al<sub>2</sub>O<sub>3</sub>-CuO borosilicate glasses were investigated by focusing on the Ce K-edge to enhance low-energy gamma-ray attenuation (15–60 keV). Five glass compositions with the nominal formula 60 B<sub>2</sub>O<sub>3</sub> – 5 Al<sub>2</sub>O<sub>3</sub> – 5 CeO<sub>2</sub> - (30-x) SiO<sub>2</sub> – x CuO (20 ≤ x ≤ 30 mol%) were synthesised via the melt-quenching method, and their structure was analysed via FTIR and SEM techniques. The mechanical properties were computed using the bond-compression and Makishima-Mackenzie models. Radiation shielding parameters (MAC, LAC, HVL, TVL, Z<sub>eff</sub>, N<sub>eff</sub>) were calculated using Phy-X/PSD over the energy range 0.015–15 MeV. XRD results revealed the amorphous nature of the prepared samples, while FTIR showed a transition from BO<sub>4</sub> to BO<sub>3</sub> units as CuO content increased. Density increment from 3.628 to 4.006 g/cm<sup>3</sup>, and Young's modulus increased from 29.7 (bond-compression model) to 56.4 (Makishima-Mackenzie model) GPa. The mass attenuation coefficient ranged from 25.32 cm<sup>2</sup>/g at 15 keV (30 mol% CuO) to 0.02 cm<sup>2</sup>/g at 15 MeV. The Ce K-edge at 40.4 keV significantly improved radiation blocking in the 40–60 keV diagnostic range, achieving over 99 % protection below 60 keV. A comparison with literature data reveals that the investigated glasses are non-toxic and suitable than lead- and bismuth-based shields in the diagnostic X-ray range, where the Ce K-edge effect offers notable benefits.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112383"},"PeriodicalIF":1.8,"publicationDate":"2025-12-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145817439","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 : 2025-12-18DOI: 10.1016/j.apradiso.2025.112389
Mohammad A. Imheidat , M.H.A. Mhareb , Feras Alnaimat , Nuriyah M. Aloufi , Ghaseb N. Makhadmeh , Amani Alsaeedi , Maram Alnakhli , Shahad Alboqmi
This work optimized the mechanical, structural, optical and radiation shielding features of a heavy borosilicate glass system by doping with varying concentrations of Nd2O3. The glass network was characterized using Fourier transform infrared (FTIR) spectroscopy, which confirmed the integration of B2O3 and SiO2 functional groups. The addition of Nd2O3 significantly improved the mechanical properties as assessed by the Makishima-Mackenzie model; the packing density and Young's modulus rose from 0.560 to 0.615 and 69.611–77.346 GPa, respectively. Additionally, radiation shielding capabilities were enhanced across the energy range of 0.03082–0.3839 MeV, as simulated by the Phy-X software. The linear attenuation coefficient at 0.3839 MeV increased from 0.968 to 1.025 cm−1, and the fast neutron removal cross section improved from 0.103 to 0.113 cm−1. These findings unequivocally show that using Nd2O3 instead of Bi2O3 is a very successful method for creating better multipurpose radiation shielding glasses.
{"title":"The optimization of the mechanical, optical, structural, and shielding features of the heavy borosilicate glass system: Role of adding Nd2O3","authors":"Mohammad A. Imheidat , M.H.A. Mhareb , Feras Alnaimat , Nuriyah M. Aloufi , Ghaseb N. Makhadmeh , Amani Alsaeedi , Maram Alnakhli , Shahad Alboqmi","doi":"10.1016/j.apradiso.2025.112389","DOIUrl":"10.1016/j.apradiso.2025.112389","url":null,"abstract":"<div><div>This work optimized the mechanical, structural, optical and radiation shielding features of a heavy borosilicate glass system by doping with varying concentrations of Nd<sub>2</sub>O<sub>3</sub>. The glass network was characterized using Fourier transform infrared (FTIR) spectroscopy, which confirmed the integration of B<sub>2</sub>O<sub>3</sub> and SiO<sub>2</sub> functional groups. The addition of Nd<sub>2</sub>O<sub>3</sub> significantly improved the mechanical properties as assessed by the Makishima-Mackenzie model; the packing density and Young's modulus rose from 0.560 to 0.615 and 69.611–77.346 GPa, respectively. Additionally, radiation shielding capabilities were enhanced across the energy range of 0.03082–0.3839 MeV, as simulated by the Phy-X software. The linear attenuation coefficient at 0.3839 MeV increased from 0.968 to 1.025 cm<sup>−1</sup>, and the fast neutron removal cross section improved from 0.103 to 0.113 cm<sup>−1</sup>. These findings unequivocally show that using Nd<sub>2</sub>O<sub>3</sub> instead of Bi<sub>2</sub>O<sub>3</sub> is a very successful method for creating better multipurpose radiation shielding glasses.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112389"},"PeriodicalIF":1.8,"publicationDate":"2025-12-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145817402","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 : 2025-12-18DOI: 10.1016/j.apradiso.2025.112384
Doan Thi Truc Quynh , Tran Nhat Nam , Vo Diep Trung Tin , Le Duc Toan , Nguyen Thanh Dat , Huynh Dinh Chuong , Hoang Duc Tam
In this study, we propose an approach for the determination of solution concentration using a low-energy photon beam of 59.54 keV emitted from a241Am source. This study aims to develop a rapid, non-destructive method for measuring the concentration of various solutions, including acids, bases, and salts. The proposed approach is based on the principle of the attenuation of gamma photon beam intensity as it traverses matter. Following this approach, we first establish a calibration curve, which is accomplished using Monte Carlo simulation. Then, a prototype of the measurement system, consisting of a NaI(Tl) detector, an 241Am radioactive source, and a solution container, was fabricated to measure the concentration of acid, base, and salt solutions. The experimental measurements are conducted by allowing the photon beam to pass through solutions and recorded by a NaI(Tl) detector. The results obtained indicate that the proposed approach can applied to measure the concentration of salt, acid, and base solutions which yields a relative deviation between the measured concentration and the reference concentration of mostly under 9 %. The observed concentration uncertainty for most of measurements is below 7 %, except for low-concentration solutions, where the uncertainty ranges from 9 % to 12 %. The findings from this study provide a different approach using low-energy gamma photon beams in determining the concentration of solution.
{"title":"Development of a gamma transmission method using a low-activity 241Am source for determining the concentrations of acid, base, and salt solutions","authors":"Doan Thi Truc Quynh , Tran Nhat Nam , Vo Diep Trung Tin , Le Duc Toan , Nguyen Thanh Dat , Huynh Dinh Chuong , Hoang Duc Tam","doi":"10.1016/j.apradiso.2025.112384","DOIUrl":"10.1016/j.apradiso.2025.112384","url":null,"abstract":"<div><div>In this study, we propose an approach for the determination of solution concentration using a low-energy photon beam of 59.54 keV emitted from a<sup>241</sup>Am source. This study aims to develop a rapid, non-destructive method for measuring the concentration of various solutions, including acids, bases, and salts. The proposed approach is based on the principle of the attenuation of gamma photon beam intensity as it traverses matter. Following this approach, we first establish a calibration curve, which is accomplished using Monte Carlo simulation. Then, a prototype of the measurement system, consisting of a NaI(Tl) detector, an <sup>241</sup>Am radioactive source, and a solution container, was fabricated to measure the concentration of acid, base, and salt solutions. The experimental measurements are conducted by allowing the photon beam to pass through solutions and recorded by a NaI(Tl) detector. The results obtained indicate that the proposed approach can applied to measure the concentration of salt, acid, and base solutions which yields a relative deviation between the measured concentration and the reference concentration of mostly under 9 %. The observed concentration uncertainty for most of measurements is below 7 %, except for low-concentration solutions, where the uncertainty ranges from 9 % to 12 %. The findings from this study provide a different approach using low-energy gamma photon beams in determining the concentration of solution.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112384"},"PeriodicalIF":1.8,"publicationDate":"2025-12-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787208","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 : 2025-12-18DOI: 10.1016/j.apradiso.2025.112388
Sidra Ghias , Khizar Hayat Satti , Abdul Jabbar , Abdulaziz Al-Anazi , Waqas Niaz , Muhammad Ibrahim , Irfan A. Soomro
The current study evaluates the radiological groundwater quality of Dera Ghazi Khan, with an emphasis on gross alpha (α) and beta (β) activity levels and their potential health risks. Twenty-one groundwater samples were obtained from different settlements close to waste disposal sites and mining centers and analyzed using a gas-flow proportional counter. The measured radioactivity levels (α: 3.76–72.28 mBq/L; β: 67.52–848.30 mBq/L) comply with the WHO (2004) standard guidelines. The calculated radiological parameters present a coherent narrative regarding potential health impacts: the average Annual Effective Dose from beta emitters (0.2 mSv/y) and the average Annual Gonadal Dose Equivalent (1.07 mSv/y) both surpassed ICRP public dose limits by factors of 2.1 and 1.07, respectively. Most importantly, the predicted Excess Lifetime Cancer Risk reached 7.5 × 10−4, which is 7.5 times higher than the internationally accepted guideline (1.0 × 10−4). This study provides baseline data for compliance with international regulations and environmental assessments, while also contributing valuable data to worldwide radiometric dose databases.
{"title":"Evaluation of radioactivity levels and lifetime cancer risk assessment in drinking water of Dera Ghazi Khan, Pakistan","authors":"Sidra Ghias , Khizar Hayat Satti , Abdul Jabbar , Abdulaziz Al-Anazi , Waqas Niaz , Muhammad Ibrahim , Irfan A. Soomro","doi":"10.1016/j.apradiso.2025.112388","DOIUrl":"10.1016/j.apradiso.2025.112388","url":null,"abstract":"<div><div>The current study evaluates the radiological groundwater quality of Dera Ghazi Khan, with an emphasis on gross alpha (α) and beta (β) activity levels and their potential health risks. Twenty-one groundwater samples were obtained from different settlements close to waste disposal sites and mining centers and analyzed using a gas-flow proportional counter. The measured radioactivity levels (α: 3.76–72.28 mBq/L; β: 67.52–848.30 mBq/L) comply with the WHO (2004) standard guidelines. The calculated radiological parameters present a coherent narrative regarding potential health impacts: the average Annual Effective Dose from beta emitters (0.2 mSv/y) and the average Annual Gonadal Dose Equivalent (1.07 mSv/y) both surpassed ICRP public dose limits by factors of 2.1 and 1.07, respectively. Most importantly, the predicted Excess Lifetime Cancer Risk reached 7.5 × 10<sup>−4</sup>, which is 7.5 times higher than the internationally accepted guideline (1.0 × 10<sup>−4</sup>). This study provides baseline data for compliance with international regulations and environmental assessments, while also contributing valuable data to worldwide radiometric dose databases.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112388"},"PeriodicalIF":1.8,"publicationDate":"2025-12-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145910296","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 : 2025-12-18DOI: 10.1016/j.apradiso.2025.112391
Geraldyne Ule-Duque , Luigi Capponi , Marat Margulis
The need for nuclear data for radioisotope production is of great importance for research and development in a wide range of applications of nuclear technology. This study presents a nuclear data sensitivity study for different radioisotopes that are used (or will be potentially used) in nuclear medicine and that are produced in nuclear reactors through neutron activation. The objective of the analysis is to understand how production is affected by targeting a new reaction cross-section region (different from the averaged cross-section that is currently being used) and determine whether the production could be maximised. The criterion determining whether a production route could be maximised is the change that the nuclide number undergoes over time when using the different cross-section values in the reaction rate equations.
{"title":"Medical radionuclide production in nuclear reactors – Sensitivity analysis to nuclear data","authors":"Geraldyne Ule-Duque , Luigi Capponi , Marat Margulis","doi":"10.1016/j.apradiso.2025.112391","DOIUrl":"10.1016/j.apradiso.2025.112391","url":null,"abstract":"<div><div>The need for nuclear data for radioisotope production is of great importance for research and development in a wide range of applications of nuclear technology. This study presents a nuclear data sensitivity study for different radioisotopes that are used (or will be potentially used) in nuclear medicine and that are produced in nuclear reactors through neutron activation. The objective of the analysis is to understand how production is affected by targeting a new reaction cross-section region (different from the averaged cross-section that is currently being used) and determine whether the production could be maximised. The criterion determining whether a production route could be maximised is the change that the nuclide number undergoes over time when using the different cross-section values in the reaction rate equations.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112391"},"PeriodicalIF":1.8,"publicationDate":"2025-12-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787269","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 : 2025-12-16DOI: 10.1016/j.apradiso.2025.112378
Ana Noguera, Rodolfo Reboulaz, Heinkel Bentos Pereira, Laura Fornaro
This study provides the first report on the activity concentrations of gamma emitters (226Ra, 232Th, and 40K) in building materials marketed and used in Uruguay, as well as their potential for 222Rn exhalation. The analyzed materials were categorized based on their use into cements and cementitious mixtures, granites, bricks and concrete blocks, ceramic and porcelain tiles, and gypsum and fiber cement. Granites were found to have the highest activity concentrations for 226Ra, 232Th, and 40K, whereas gypsum and fiber cement exhibited the lowest activity concentrations for all three radionuclides. Additionally, granites have the highest potential for 222Rn exhalation and radiological indices. Radiological indexes and dose evaluation show that the building materials analyzed present no radiological risk.
{"title":"Assessing gamma emitters and 222Rn exhalation in Uruguayan building materials: a comprehensive analysis","authors":"Ana Noguera, Rodolfo Reboulaz, Heinkel Bentos Pereira, Laura Fornaro","doi":"10.1016/j.apradiso.2025.112378","DOIUrl":"10.1016/j.apradiso.2025.112378","url":null,"abstract":"<div><div>This study provides the first report on the activity concentrations of gamma emitters (<sup>226</sup>Ra, <sup>232</sup>Th, and <sup>40</sup>K) in building materials marketed and used in Uruguay, as well as their potential for <sup>222</sup>Rn exhalation. The analyzed materials were categorized based on their use into cements and cementitious mixtures, granites, bricks and concrete blocks, ceramic and porcelain tiles, and gypsum and fiber cement. Granites were found to have the highest activity concentrations for <sup>226</sup>Ra, <sup>232</sup>Th, and <sup>40</sup>K, whereas gypsum and fiber cement exhibited the lowest activity concentrations for all three radionuclides. Additionally, granites have the highest potential for <sup>222</sup>Rn exhalation and radiological indices. Radiological indexes and dose evaluation show that the building materials analyzed present no radiological risk.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112378"},"PeriodicalIF":1.8,"publicationDate":"2025-12-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787265","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 : 2025-12-16DOI: 10.1016/j.apradiso.2025.112381
Anderson M.B. Silva , Danilo O. Junot , Patrícia L. Antonio , Divanizia N. Souza , Linda V.E. Caldas
The luminescence properties of crystalline materials are critical for monitoring physical phenomena, including ionizing radiation doses. In this study, CaSO4:Mn,Tb phosphors were synthesized using four distinct methods: solid-state diffusion, co-precipitation, sol-gel, and slow evaporation routes. The influence of synthesis conditions on the structural, morphological, elemental, and luminescent properties of the phosphors was systematically investigated. X-ray diffraction (XRD) patterns confirmed that all synthesis routes produced samples with a stable CaSO4 crystal phase, and doping with Tb3+ and Mn2+ did not alter the crystal structure. Scanning electron microscopy (SEM) images revealed that synthesis methods significantly influenced grain morphology. Energy-dispersive X-ray spectroscopy (EDS) spectra validated the successful incorporation of Tb3+ and Mn2+ ions into the crystal lattice. The slow evaporation route, followed by co-precipitation, yielded the highest intensity of thermoluminescence (TL) glow curves, which were characterized using Schott BG-39 and Hoya U-340 bandpass filters to control wavelengths. Different emission curve behaviors for TL were observed. In the optically stimulated luminescence (OSL) analyses, obtained with continuous intensity optical stimulation and a 40 s integration time, all samples exhibited an exponential decrease in OSL signal as the charge traps were emptied. The CaSO4:Mn,Tb phosphor produced via the sol-gel route, and that synthesized by slow evaporation, showed the highest OSL intensity, followed by those produced via co-precipitation and solid-state synthesis. However, the high coefficient of variation (CV) in TL/OSL responses of samples produced by sol-gel and co-precipitation methods limited the reproducibility of the luminescent measurements. The slow evaporation route emerged as the most consistent and efficient method, exhibiting low CV values (<10 %) in terms of signal variation and sensitivity, the highest linear correlation in the dose-response relationship over the irradiation range of 0.16 Gy–100 Gy, and greater TL signal stability for long-term applications.
{"title":"Analysis of dosimetric characteristics of CaSO4:Mn,Tb phosphors synthesized by four different routes","authors":"Anderson M.B. Silva , Danilo O. Junot , Patrícia L. Antonio , Divanizia N. Souza , Linda V.E. Caldas","doi":"10.1016/j.apradiso.2025.112381","DOIUrl":"10.1016/j.apradiso.2025.112381","url":null,"abstract":"<div><div>The luminescence properties of crystalline materials are critical for monitoring physical phenomena, including ionizing radiation doses. In this study, CaSO<sub>4</sub>:Mn,Tb phosphors were synthesized using four distinct methods: solid-state diffusion, co-precipitation, sol-gel, and slow evaporation routes. The influence of synthesis conditions on the structural, morphological, elemental, and luminescent properties of the phosphors was systematically investigated. X-ray diffraction (XRD) patterns confirmed that all synthesis routes produced samples with a stable CaSO<sub>4</sub> crystal phase, and doping with Tb<sup>3+</sup> and Mn<sup>2+</sup> did not alter the crystal structure. Scanning electron microscopy (SEM) images revealed that synthesis methods significantly influenced grain morphology. Energy-dispersive X-ray spectroscopy (EDS) spectra validated the successful incorporation of Tb<sup>3+</sup> and Mn<sup>2+</sup> ions into the crystal lattice. The slow evaporation route, followed by co-precipitation, yielded the highest intensity of thermoluminescence (TL) glow curves, which were characterized using Schott BG-39 and Hoya U-340 bandpass filters to control wavelengths. Different emission curve behaviors for TL were observed. In the optically stimulated luminescence (OSL) analyses, obtained with continuous intensity optical stimulation and a 40 s integration time, all samples exhibited an exponential decrease in OSL signal as the charge traps were emptied. The CaSO<sub>4</sub>:Mn,Tb phosphor produced via the sol-gel route, and that synthesized by slow evaporation, showed the highest OSL intensity, followed by those produced via co-precipitation and solid-state synthesis. However, the high coefficient of variation (CV) in TL/OSL responses of samples produced by sol-gel and co-precipitation methods limited the reproducibility of the luminescent measurements. The slow evaporation route emerged as the most consistent and efficient method, exhibiting low CV values (<10 %) in terms of signal variation and sensitivity, the highest linear correlation in the dose-response relationship over the irradiation range of 0.16 Gy–100 Gy, and greater TL signal stability for long-term applications.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"229 ","pages":"Article 112381"},"PeriodicalIF":1.8,"publicationDate":"2025-12-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787205","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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