Pub Date : 2025-01-03DOI: 10.1016/j.radphyschem.2024.112495
Hadi Zanganeh, M.N. Nasrabadi
In this work, the IECF device using the MCNPX code was simulated and parameters such as lethargy as well as cross-sections, changes in neutron flux and dosimetry and suitable multi-layer shields were studied. To secure the device from radiation hazards at different work intensities and in addition to the role of shielding, the role of producing materials such as lithium, the required simulations were done and the necessary shield thicknesses were determined. From the intensity of <mml:math altimg="si1.svg"><mml:mrow><mml:msup><mml:mn>10</mml:mn><mml:mn>6</mml:mn></mml:msup><mml:msup><mml:mi>s</mml:mi><mml:mrow><mml:mo>−</mml:mo><mml:mn>1</mml:mn></mml:mrow></mml:msup></mml:mrow></mml:math> which is used for nuclear laboratories in universities up to neutron production <mml:math altimg="si2.svg"><mml:mrow><mml:msup><mml:mn>10</mml:mn><mml:mn>12</mml:mn></mml:msup><mml:msup><mml:mi>s</mml:mi><mml:mrow><mml:mo>−</mml:mo><mml:mn>1</mml:mn></mml:mrow></mml:msup></mml:mrow></mml:math> which is used for the BNCT method, an optimal shield thickness is required. For the first layer, a material with an average mass number was chosen to absorb the highest amount of energy and produce the lowest amount of gamma in inelastic scattering with fast neutrons. The produced gammas are also absorbed by concrete. For the thickness changes of different layers, in addition to measuring the remaining energies in the neutron flux, the cross-sections corresponding to those energies were also measured in order to calculate the required shield thicknesses for different powers of the device in different working conditions. After determining the type of different materials suitable for shielding, dosimetry was performed according to the ICRP60 standard and by making the necessary changes in the thickness of the layers, the neutron and gamma doses were reduced to the standard level. Also, the fluxes of thermal, epithermal and fast neutrons were measured in different shielding layers. Finally, for all calculated neutron production intensities, the necessary shielding thickness was determined for safe operation of the device. As a result of this study, by modifying and improving the method of determining the required thickness of the shield for different intensities, the smaller and more suitable thickness for the intensity of 10<ce:sup loc="post">9</ce:sup><mml:math altimg="si3.svg"><mml:mrow><mml:msup><mml:mi mathvariant="normal">s</mml:mi><mml:mrow><mml:mo>−</mml:mo><mml:mn>1</mml:mn></mml:mrow></mml:msup></mml:mrow></mml:math> was determined. This improvement and reduction in the thickness of the shield caused a reduction in the weight of the total shield and a reduction in the cost of shield construction while maintaining radiation safety according to ICRP60 standards. The idea of lithium production by IECF device using the materials of this shielding was simulated by MCNPX code. Boric acid was investigated and studied as a suitable material for lithium production. After pe
{"title":"Simulation of a suitable neutron and gamma shield for IECF device in different working modes by MCNPX code and studying its lithium production","authors":"Hadi Zanganeh, M.N. Nasrabadi","doi":"10.1016/j.radphyschem.2024.112495","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2024.112495","url":null,"abstract":"In this work, the IECF device using the MCNPX code was simulated and parameters such as lethargy as well as cross-sections, changes in neutron flux and dosimetry and suitable multi-layer shields were studied. To secure the device from radiation hazards at different work intensities and in addition to the role of shielding, the role of producing materials such as lithium, the required simulations were done and the necessary shield thicknesses were determined. From the intensity of <mml:math altimg=\"si1.svg\"><mml:mrow><mml:msup><mml:mn>10</mml:mn><mml:mn>6</mml:mn></mml:msup><mml:msup><mml:mi>s</mml:mi><mml:mrow><mml:mo>−</mml:mo><mml:mn>1</mml:mn></mml:mrow></mml:msup></mml:mrow></mml:math> which is used for nuclear laboratories in universities up to neutron production <mml:math altimg=\"si2.svg\"><mml:mrow><mml:msup><mml:mn>10</mml:mn><mml:mn>12</mml:mn></mml:msup><mml:msup><mml:mi>s</mml:mi><mml:mrow><mml:mo>−</mml:mo><mml:mn>1</mml:mn></mml:mrow></mml:msup></mml:mrow></mml:math> which is used for the BNCT method, an optimal shield thickness is required. For the first layer, a material with an average mass number was chosen to absorb the highest amount of energy and produce the lowest amount of gamma in inelastic scattering with fast neutrons. The produced gammas are also absorbed by concrete. For the thickness changes of different layers, in addition to measuring the remaining energies in the neutron flux, the cross-sections corresponding to those energies were also measured in order to calculate the required shield thicknesses for different powers of the device in different working conditions. After determining the type of different materials suitable for shielding, dosimetry was performed according to the ICRP60 standard and by making the necessary changes in the thickness of the layers, the neutron and gamma doses were reduced to the standard level. Also, the fluxes of thermal, epithermal and fast neutrons were measured in different shielding layers. Finally, for all calculated neutron production intensities, the necessary shielding thickness was determined for safe operation of the device. As a result of this study, by modifying and improving the method of determining the required thickness of the shield for different intensities, the smaller and more suitable thickness for the intensity of 10<ce:sup loc=\"post\">9</ce:sup><mml:math altimg=\"si3.svg\"><mml:mrow><mml:msup><mml:mi mathvariant=\"normal\">s</mml:mi><mml:mrow><mml:mo>−</mml:mo><mml:mn>1</mml:mn></mml:mrow></mml:msup></mml:mrow></mml:math> was determined. This improvement and reduction in the thickness of the shield caused a reduction in the weight of the total shield and a reduction in the cost of shield construction while maintaining radiation safety according to ICRP60 standards. The idea of lithium production by IECF device using the materials of this shielding was simulated by MCNPX code. Boric acid was investigated and studied as a suitable material for lithium production. After pe","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"9 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2025-01-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142967741","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Estimation of internal dose is a critical task in nuclear medicine and radiation protection. New organ-specific features are included to construct a machine learning model capable of predicting the internal dose in the UF/NCI voxel phantoms, ranging from newborn to pediatric and adult of both genders. The dosimetry data is generated using the Monte Carlo simulation toolkit, Gate. Multiple source organs were utilized to train and validate the predictive models. Results demonstrate high accuracy, with less than 2% Root Squared Error in predicting the internal dose in most organs using the XGBoost machine learning model. This research can help nuclear medicine and radiation protection researchers and practitioners refine internal dose predictions based on anatomical and physiological characteristics of patients.
{"title":"Voxel-based internal dose prediction using machine learning with organ-specific features and Monte Carlo simulations","authors":"Khaled Belkadhi, Nabil Chaabane, Kais Manai, Omrane Kadri","doi":"10.1016/j.radphyschem.2024.112497","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2024.112497","url":null,"abstract":"Estimation of internal dose is a critical task in nuclear medicine and radiation protection. New organ-specific features are included to construct a machine learning model capable of predicting the internal dose in the UF/NCI voxel phantoms, ranging from newborn to pediatric and adult of both genders. The dosimetry data is generated using the Monte Carlo simulation toolkit, Gate. Multiple source organs were utilized to train and validate the predictive models. Results demonstrate high accuracy, with less than 2% Root Squared Error in predicting the internal dose in most organs using the XGBoost machine learning model. This research can help nuclear medicine and radiation protection researchers and practitioners refine internal dose predictions based on anatomical and physiological characteristics of patients.","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"22 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2025-01-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142967851","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
We synthesized the 0.01, 0.05, 0.1, and 0.5% Mn-doped ZnAl2O4 transparent ceramics of a spinel structure by the spark plasma sintering method and evaluated their optical, scintillation, and dosimetric properties. The XRD patterns confirmed that ZnAl2O4 was successfully synthesized. Photoluminescence spectra showed a broad emission band due to the 3d-3d transitions of Mn2+ ions. In the thermally stimulated luminescence (TSL) properties, TSL glow peaks of the Mn-doped ZnAl2O4 transparent ceramics were detected at 160, 320, and 490 °C. TSL spectra of all the samples heated at 160 °C showed the emission peak at 520 nm due to the Mn2+ ions. The TSL and OSL intensities of the 0.05% Mn-doped samples were the highest in all the samples. In the 0.05% Mn-doped sample, the TSL and OSL dose response functions exhibited a linear response at 0.01–100 and 1–100 mGy, respectively.
{"title":"Mn concentration dependence on dosimetric properties of Mn-doped ZnAl2O4 transparent ceramics","authors":"Satoshi Honjo, Kensei Ichiba, Yusuke Endo, Takumi Kato, Daisuke Nakauchi, Noriaki Kawaguchi, Takayuki Yanagida","doi":"10.1016/j.radphyschem.2025.112513","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2025.112513","url":null,"abstract":"We synthesized the 0.01, 0.05, 0.1, and 0.5% Mn-doped ZnAl<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">4</ce:inf> transparent ceramics of a spinel structure by the spark plasma sintering method and evaluated their optical, scintillation, and dosimetric properties. The XRD patterns confirmed that ZnAl<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">4</ce:inf> was successfully synthesized. Photoluminescence spectra showed a broad emission band due to the 3d-3d transitions of Mn<ce:sup loc=\"post\">2+</ce:sup> ions. In the thermally stimulated luminescence (TSL) properties, TSL glow peaks of the Mn-doped ZnAl<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">4</ce:inf> transparent ceramics were detected at 160, 320, and 490 °C. TSL spectra of all the samples heated at 160 °C showed the emission peak at 520 nm due to the Mn<ce:sup loc=\"post\">2+</ce:sup> ions. The TSL and OSL intensities of the 0.05% Mn-doped samples were the highest in all the samples. In the 0.05% Mn-doped sample, the TSL and OSL dose response functions exhibited a linear response at 0.01–100 and 1–100 mGy, respectively.","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"11 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2025-01-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142967850","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-01-02DOI: 10.1016/j.radphyschem.2025.112509
R. Hauko, J. Padežnik Gomilšek, A. Kodre, I. Arčon, U. Luin
Analysis of the recently measured absorption spectra of molecular HI at K and L edges of iodine, in parallel with previously measured spectra of noble gas Xe and the K edge spectrum of atomic I, is presented. A strong dependence of some valence multielectron photoexcitation features on the orbital momentum of the core vacancy is found, attributed to the change of the symmetry of the HI molecule: the shake-up coexcitation of a valence electron to a free molecular orbital is much stronger at L3 than L1 edge. The effect of angular momentum of the core hole on the shake processes of deeper multielectron photoexcitations is found negligible. Both HI and Xe exhibit a much weaker one-electron transition [1s]6p than monatomic I. At the K edge, the strength of coexcitations of 4d, 4p and 3d subshells in atomic I is close to the HI and Xe. The same is found for HI and Xe at the L edges, due to a weak contribution of the additional free molecular orbital in HI.
{"title":"Iodine K- and L-edge X-ray absorption spectra of HI: The effect of molecular orbitals and core subshells","authors":"R. Hauko, J. Padežnik Gomilšek, A. Kodre, I. Arčon, U. Luin","doi":"10.1016/j.radphyschem.2025.112509","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2025.112509","url":null,"abstract":"Analysis of the recently measured absorption spectra of molecular HI at <ce:italic>K</ce:italic> and <ce:italic>L</ce:italic> edges of iodine, in parallel with previously measured spectra of noble gas Xe and the <ce:italic>K</ce:italic> edge spectrum of atomic I, is presented. A strong dependence of some valence multielectron photoexcitation features on the orbital momentum of the core vacancy is found, attributed to the change of the symmetry of the HI molecule: the shake-up coexcitation of a valence electron to a free molecular orbital is much stronger at <ce:italic>L</ce:italic><ce:inf loc=\"post\">3</ce:inf> than <ce:italic>L</ce:italic><ce:inf loc=\"post\">1</ce:inf> edge. The effect of angular momentum of the core hole on the shake processes of deeper multielectron photoexcitations is found negligible. Both HI and Xe exhibit a much weaker one-electron transition [1<ce:italic>s</ce:italic>]6<ce:italic>p</ce:italic> than monatomic I. At the <ce:italic>K</ce:italic> edge, the strength of coexcitations of 4<ce:italic>d</ce:italic>, 4<ce:italic>p</ce:italic> and 3<ce:italic>d</ce:italic> subshells in atomic I is close to the HI and Xe. The same is found for HI and Xe at the <ce:italic>L</ce:italic> edges, due to a weak contribution of the additional free molecular orbital in HI.","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"9 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2025-01-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142967852","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-01-02DOI: 10.1016/j.radphyschem.2024.112490
Sergio Biancotto, Marco D'Arienzo
A large release of radioactive material, consequence of a supposed nuclear power plant (NPP) accident, is simulated in the densely populated and productive area of the Italian Po Valley, using wind speed and atmospheric stability conditions characteristic of the region. The first step of the analysis is the evaluation of the dose received by the public during the plume passage through the HotSpot code. The second step is the calculation of dose in the years following the accident through the RESRAD-ONSITE code, considering soil and food-chain contamination. The third step is the dose reduction obtained with protective actions, mainly iodine prophylaxis and shelter in place. Recommendations contained in the International Commission on Radiological Protection (ICRP) Publication 146 are applied, with the goal of maintaining the public dose below the ICRP recommended Reference Levels. The influence of the height of the release is also analyzed. Without implementing protective measures, the public may be exposed to a dose of up to 2.9 × 102 mSv, although this is confined to a fairly restricted area. However, the dose can be greatly reduced by appropriate and preplanned protective actions. The use of ICRP Reference Levels is of overwhelming importance in guiding protective actions and helping authorities to make balanced decisions.
{"title":"Postulated nuclear power plant accident in the Po valley (Italy) and application of the ICRP publication 146 recommendations","authors":"Sergio Biancotto, Marco D'Arienzo","doi":"10.1016/j.radphyschem.2024.112490","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2024.112490","url":null,"abstract":"A large release of radioactive material, consequence of a supposed nuclear power plant (NPP) accident, is simulated in the densely populated and productive area of the Italian Po Valley, using wind speed and atmospheric stability conditions characteristic of the region. The first step of the analysis is the evaluation of the dose received by the public during the plume passage through the HotSpot code. The second step is the calculation of dose in the years following the accident through the RESRAD-ONSITE code, considering soil and food-chain contamination. The third step is the dose reduction obtained with protective actions, mainly iodine prophylaxis and shelter in place. Recommendations contained in the International Commission on Radiological Protection (ICRP) Publication 146 are applied, with the goal of maintaining the public dose below the ICRP recommended Reference Levels. The influence of the height of the release is also analyzed. Without implementing protective measures, the public may be exposed to a dose of up to 2.9 × 10<ce:sup loc=\"post\">2</ce:sup> mSv, although this is confined to a fairly restricted area. However, the dose can be greatly reduced by appropriate and preplanned protective actions. The use of ICRP Reference Levels is of overwhelming importance in guiding protective actions and helping authorities to make balanced decisions.","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"45 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2025-01-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142967853","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-01-01DOI: 10.1016/j.radphyschem.2024.112496
Cansu Karakaya, Ediz Ercenk, Senol Yilmaz
This study examined the physical and radiation shielding properties of compounds formed by adding 0–50 wt % Bi2O3 to blast furnace slag. Physical properties: density included molar volume, oxygen molar volume, and oxygen packing density were calculated. The radiation protection properties of the prepared glasses were calculated theoretically using Phy-X/PSD software. Experimental shielding measurements were also made at some energy levels to verify the shielding values. The addition of Bi2O3 increased the composition density from 2.87 to 4.54 g/cm3. Mass attenuation coefficient (MAC) results showed increased radiation shielding performance with adding Bi2O3. While the highest MAC value for the pure composition was 1.222 cm2/g, the lowest was calculated as 0.054 cm2/g for the sample with 50% Bi2O3 added by weight. In addition, effective atomic charge (Zeff) and electron densities (Neff) were also determined, and it was observed that these values increased significantly with the addition of Bi2O3. Fast neutron removal cross-section values of the compositions were determined and compared with some commercial/alternative shielding materials.
{"title":"Is blast furnace slag suitable for the production of radiation shielding glass?","authors":"Cansu Karakaya, Ediz Ercenk, Senol Yilmaz","doi":"10.1016/j.radphyschem.2024.112496","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2024.112496","url":null,"abstract":"This study examined the physical and radiation shielding properties of compounds formed by adding 0–50 wt % Bi<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> to blast furnace slag. Physical properties: density included molar volume, oxygen molar volume, and oxygen packing density were calculated. The radiation protection properties of the prepared glasses were calculated theoretically using Phy-X/PSD software. Experimental shielding measurements were also made at some energy levels to verify the shielding values. The addition of Bi<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> increased the composition density from 2.87 to 4.54 g/cm<ce:sup loc=\"post\">3</ce:sup>. Mass attenuation coefficient (MAC) results showed increased radiation shielding performance with adding Bi<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf>. While the highest MAC value for the pure composition was 1.222 cm<ce:sup loc=\"post\">2</ce:sup>/g, the lowest was calculated as 0.054 cm<ce:sup loc=\"post\">2</ce:sup>/g for the sample with 50% Bi<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> added by weight. In addition, effective atomic charge (Z<ce:inf loc=\"post\">eff</ce:inf>) and electron densities (N<ce:inf loc=\"post\">eff</ce:inf>) were also determined, and it was observed that these values increased significantly with the addition of Bi<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf>. Fast neutron removal cross-section values of the compositions were determined and compared with some commercial/alternative shielding materials.","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"5 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2025-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142925297","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-12-31DOI: 10.1016/j.radphyschem.2024.112506
Chin Lok Sheng, Muhammad Arif Sazali, Asyraf Arif Abu Bakar, Ahmad Hambali Ismail, Roslan Yahya, Muhammad Syahir Sarkawi, Nur Syazwani Mohd Ali, Khairulnadzmi Jamaluddin
Radiation shielding is crucial to ensuring the safety of the people and the environment. Concrete and lead are common materials with great shielding properties against gamma and neutron radiation, yet they have drawbacks such as being harmful to human health, high cost, and seismic vulnerability. Therefore, the aim of this study is to develop polyethylene (PE)-based composites doped with cadmium (Cd) and tungsten oxide (WO3), to determine the neutron-gamma shielding properties of the composites, and to compare the radiation shielding performance of multilayer shielding of the composites and the base PE. The composites were fabricated using the melt-mixing and hot-pressing methods. They were characterized using X-ray diffraction, micro-computed tomography scanning, and field emission scanning electron microscopy to observe the dispersion of filler particles in the PE matrix. Results show that the filler elements have good distribution in the composite. Their shielding performance was evaluated using the 241Am/Be neutron and 137Cs gamma sources at the Malaysian Nuclear Agency. The results show that the PE+20% WO3 has the highest values of neutron removal macroscopic cross-section and gamma linear attenuation coefficient for single-layer shielding. For multilayer configuration, PE+10%Cd with PE+10% WO3 (Cd10/W10) has the best mixed neutron-gamma radiation attenuation performance. The results will help in the development of alternative materials for better radiation protection.
{"title":"Polyethylene composite doped with cadmium and tungsten oxide for neutron-gamma multilayer shielding","authors":"Chin Lok Sheng, Muhammad Arif Sazali, Asyraf Arif Abu Bakar, Ahmad Hambali Ismail, Roslan Yahya, Muhammad Syahir Sarkawi, Nur Syazwani Mohd Ali, Khairulnadzmi Jamaluddin","doi":"10.1016/j.radphyschem.2024.112506","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2024.112506","url":null,"abstract":"Radiation shielding is crucial to ensuring the safety of the people and the environment. Concrete and lead are common materials with great shielding properties against gamma and neutron radiation, yet they have drawbacks such as being harmful to human health, high cost, and seismic vulnerability. Therefore, the aim of this study is to develop polyethylene (PE)-based composites doped with cadmium (Cd) and tungsten oxide (WO<ce:inf loc=\"post\">3</ce:inf>), to determine the neutron-gamma shielding properties of the composites, and to compare the radiation shielding performance of multilayer shielding of the composites and the base PE. The composites were fabricated using the melt-mixing and hot-pressing methods. They were characterized using X-ray diffraction, micro-computed tomography scanning, and field emission scanning electron microscopy to observe the dispersion of filler particles in the PE matrix. Results show that the filler elements have good distribution in the composite. Their shielding performance was evaluated using the <ce:sup loc=\"post\">241</ce:sup>Am/Be neutron and <ce:sup loc=\"post\">137</ce:sup>Cs gamma sources at the Malaysian Nuclear Agency. The results show that the PE+20% WO<ce:inf loc=\"post\">3</ce:inf> has the highest values of neutron removal macroscopic cross-section and gamma linear attenuation coefficient for single-layer shielding. For multilayer configuration, PE+10%Cd with PE+10% WO<ce:inf loc=\"post\">3</ce:inf> (Cd10/W10) has the best mixed neutron-gamma radiation attenuation performance. The results will help in the development of alternative materials for better radiation protection.","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"398 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2024-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142925298","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-12-31DOI: 10.1016/j.radphyschem.2024.112505
M.N. Vishnu Narayanan Namboothiri, K.A. Naseer, K. Marimuthu, M.I. Sayyed, A.F. Abd El-Rehim
A brand new series of Eu3+ ions blended Li–Al borophospho-silictae glass matrix were synthesized by conventional melt quenching technique for radiation protection applications. XRD and FTIR characteristic profiles were recorded to confirm the amorphous nature and to analyze the geometrical configuration due to the functional groups occurrence in the prepared glasses. Physical properties were calculated and reported. Greater rigidity of the titled glasses was exposed by the structural attributes. The results obtained from the mechanical properties reveal the compactness of the Europium incorporated multi-modifier Li–Al borophospho-silicate glasses. The optical band gap studies for the titled glasses were carried out by employing Tauc's plot method, and the band gap values for direct and indirect transitions were calculated, discussed and reported. The radiation shielding ability of the glasses has been determined. In the middle energy range, the MAC values of the glasses are all very close together, within 0.001 cm2/g between 0.077 and 0.078 cm2/g. The HVLs of the tested glasses at energies starting at 0.511 are in the following order: PBSACa > PBSASr > PBSABa > PBSAZn > PBSACd.
{"title":"Fabrication, structural features and radiation prevention potential of Europium incorporated multi-modifier Li–Al borophospho-silicate glasses","authors":"M.N. Vishnu Narayanan Namboothiri, K.A. Naseer, K. Marimuthu, M.I. Sayyed, A.F. Abd El-Rehim","doi":"10.1016/j.radphyschem.2024.112505","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2024.112505","url":null,"abstract":"A brand new series of Eu<ce:sup loc=\"post\">3+</ce:sup> ions blended Li–Al borophospho-silictae glass matrix were synthesized by conventional melt quenching technique for radiation protection applications. XRD and FTIR characteristic profiles were recorded to confirm the amorphous nature and to analyze the geometrical configuration due to the functional groups occurrence in the prepared glasses. Physical properties were calculated and reported. Greater rigidity of the titled glasses was exposed by the structural attributes. The results obtained from the mechanical properties reveal the compactness of the Europium incorporated multi-modifier Li–Al borophospho-silicate glasses. The optical band gap studies for the titled glasses were carried out by employing Tauc's plot method, and the band gap values for direct and indirect transitions were calculated, discussed and reported. The radiation shielding ability of the glasses has been determined. In the middle energy range, the MAC values of the glasses are all very close together, within 0.001 cm<ce:sup loc=\"post\">2</ce:sup>/g between 0.077 and 0.078 cm<ce:sup loc=\"post\">2</ce:sup>/g. The HVLs of the tested glasses at energies starting at 0.511 are in the following order: PBSACa > PBSASr > PBSABa > PBSAZn > PBSACd.","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"160 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2024-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142925317","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-12-31DOI: 10.1016/j.radphyschem.2024.112508
M.I. Sayyed, K.A. Mahmoud, Shrikant Biradar
A new boro-tellurite glass series doped with BaO and Er2O3 was fabricated according to the chemical formula of (21+x) BaO + 14Bi2O3 + (60-x-y) B2O3 + 5TeO2 + y Er2O3 for optical and radiation shielding applications, where y = 0, 1, 2, and 3 mol% and x = 0, 2, 4, and 6 mol%. The UV–Vis spectra for the prepared samples were detected using the spectrophotometer over a wavenumber interval of 300–1000 nm. Based on the absorption spectra, several factors related to the optical properties, including band gap, Urbach energy, refractive index, dielectric constant, reflection loss, optical transmission, and molar refraction, were computed. The increase in BaO–Er2O3 content throughout 21–30 mol% increases the refractive index from 2.445 to 2.520. Additionally, the impact of the substitution of B2O3 by BaO–Er2O3 on the radiation shielding properties of prepared glasses was examined over an energy interval of 0.015–15 MeV. The increase in BaO + Er2O3 across the concentration of 21–30 mol% raises the linear attention coefficient of prepared boro-tellurite glasses between 257.819 and 302.334 cm-1 at 0.015 MeV. The LAC enhancement is accompanied by a decreased thickness of the half-value layer, which reduced from 4.659 cm to 4.194 cm at 15 MeV when the BaO + Er2O3 concentrations raised throughout 21–30 mol%, respectively.
{"title":"Synergistic effects of erbium and barium oxides on optical and gamma-ray shielding characteristic of boro-tellurite glasses","authors":"M.I. Sayyed, K.A. Mahmoud, Shrikant Biradar","doi":"10.1016/j.radphyschem.2024.112508","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2024.112508","url":null,"abstract":"A new boro-tellurite glass series doped with BaO and Er<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> was fabricated according to the chemical formula of (21+x) BaO + 14Bi<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> + (60-x-y) B<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> + 5TeO<ce:inf loc=\"post\">2</ce:inf> + y Er<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> for optical and radiation shielding applications, where y = 0, 1, 2, and 3 mol% and x = 0, 2, 4, and 6 mol%. The UV–Vis spectra for the prepared samples were detected using the spectrophotometer over a wavenumber interval of 300–1000 nm. Based on the absorption spectra, several factors related to the optical properties, including band gap, Urbach energy, refractive index, dielectric constant, reflection loss, optical transmission, and molar refraction, were computed. The increase in BaO–Er<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> content throughout 21–30 mol% increases the refractive index from 2.445 to 2.520. Additionally, the impact of the substitution of B<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> by BaO–Er<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> on the radiation shielding properties of prepared glasses was examined over an energy interval of 0.015–15 MeV. The increase in BaO + Er<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> across the concentration of 21–30 mol% raises the linear attention coefficient of prepared boro-tellurite glasses between 257.819 and 302.334 cm-1 at 0.015 MeV. The LAC enhancement is accompanied by a decreased thickness of the half-value layer, which reduced from 4.659 cm to 4.194 cm at 15 MeV when the BaO + Er<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> concentrations raised throughout 21–30 mol%, respectively.","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"9 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2024-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142967856","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-12-31DOI: 10.1016/j.radphyschem.2024.112504
Mukesh Kumar Rathore, Dileep Kumar Manghwani, Wang Dan, Abeera Moin, Mahmooda Buriro, Rabia Faridi
Electron Beam Irradiation (EBI) is a non-thermal food processing and preservation technique that can be used to decontaminate the microbial load of perishable roots of Radix ophiopogonis (OR). Thus, preserve its nutrients constituents.
{"title":"Influence of different doses of electron beam irradiation on microbial load and physiochemical attributes of Radix ophiopogonis (Ophiopogon japonicas)","authors":"Mukesh Kumar Rathore, Dileep Kumar Manghwani, Wang Dan, Abeera Moin, Mahmooda Buriro, Rabia Faridi","doi":"10.1016/j.radphyschem.2024.112504","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2024.112504","url":null,"abstract":"Electron Beam Irradiation (EBI) is a non-thermal food processing and preservation technique that can be used to decontaminate the microbial load of perishable roots of Radix ophiopogonis (OR). Thus, preserve its nutrients constituents.","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"55 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2024-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142925276","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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