Building on our previous study of structural, and electrical properties of Na2O–B2O3–P2O5 work investigates their γ-ray shielding performance. Glasses with compositions 30Na2O – (70-y) B2O3–y P2O5 (where y = 0, 14, 21, and 35 mol%) were analyzed using the Phy-X/PSD software to determine the attenuation and penetration factors of this glass system at different energies. The linear attenuation coefficient (LAC) values were found to decrease exponentially with increasing energy, ranging from 0.124 to 0.089 cm−1 for 30Na2O – 70 B2O3 and from 0.138 to 0.099 cm−1 for y = 35 mol%. The addition of phosphorus pentoxide (P2O5) led to an increase in LAC values from 0.174 to 0.193 cm−1 at 0.662 MeV. The effective atomic number (Zeff) results indicated a higher probability of photon interaction with increased P2O5 content. The maximum Zeff was recorded at 0.284 MeV, with values of 7.46 for NBP1 and 8.92 for y = 35 mol%. The Phy-X/PSD program was also used to calculate the half-value layer (HVL) for the evaluated glasses in the energy range of 0.284–2.506 MeV. The HVL results showed that more gamma rays were shielded at 0.284 MeV, while photon shielding efficiency decreased with increasing energy. The tenth-value layer (TVL) values decreased with higher P2O5 concentrations but increased with higher energy. The phosphate rich glass (y = 35 mol%) exhibited the lowest TVL values (8.401 cm at 0.284 MeV, 11.928 cm at 0.662 MeV, and 16.355 cm at 1.275 MeV) and thus shows an excellent gamma-rays shielding properties. These findings demonstrate that P2O5 incorporation strengthens the glass network and enhances the γ-ray shielding capability, positioning borophosphate glasses as promising lead-free shielding materials.
{"title":"Impact of P2O5 concentration on gamma-ray shielding in Na2O–B2O3-P2O5 glass","authors":"Issam Idrissi Janati , Rodouan Touti , Mohamed Naji , Abdellah Tahiri","doi":"10.1016/j.nucana.2025.100198","DOIUrl":"10.1016/j.nucana.2025.100198","url":null,"abstract":"<div><div>Building on our previous study of structural, and electrical properties of Na<sub>2</sub>O–B<sub>2</sub>O<sub>3</sub>–P<sub>2</sub>O<sub>5</sub> work investigates their γ-ray shielding performance. Glasses with compositions 30Na<sub>2</sub>O – (70-y) B<sub>2</sub>O<sub>3</sub>–y P<sub>2</sub>O<sub>5</sub> (where y = 0, 14, 21, and 35 mol%) were analyzed using the Phy-X/PSD software to determine the attenuation and penetration factors of this glass system at different energies. The linear attenuation coefficient (LAC) values were found to decrease exponentially with increasing energy, ranging from 0.124 to 0.089 cm<sup>−1</sup> for 30Na<sub>2</sub>O – 70 B<sub>2</sub>O<sub>3</sub> and from 0.138 to 0.099 cm<sup>−1</sup> for y = 35 mol%. The addition of phosphorus pentoxide (P<sub>2</sub>O<sub>5</sub>) led to an increase in LAC values from 0.174 to 0.193 cm<sup>−1</sup> at 0.662 MeV. The effective atomic number (Z<sub>eff</sub>) results indicated a higher probability of photon interaction with increased P<sub>2</sub>O<sub>5</sub> content. The maximum Z<sub>eff</sub> was recorded at 0.284 MeV, with values of 7.46 for NBP1 and 8.92 for y = 35 mol%. The Phy-X/PSD program was also used to calculate the half-value layer (HVL) for the evaluated glasses in the energy range of 0.284–2.506 MeV. The HVL results showed that more gamma rays were shielded at 0.284 MeV, while photon shielding efficiency decreased with increasing energy. The tenth-value layer (TVL) values decreased with higher P<sub>2</sub>O<sub>5</sub> concentrations but increased with higher energy. The phosphate rich glass (y = 35 mol%) exhibited the lowest TVL values (8.401 cm at 0.284 MeV, 11.928 cm at 0.662 MeV, and 16.355 cm at 1.275 MeV) and thus shows an excellent gamma-rays shielding properties. These findings demonstrate that P<sub>2</sub>O<sub>5</sub> incorporation strengthens the glass network and enhances the γ-ray shielding capability, positioning borophosphate glasses as promising lead-free shielding materials.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 4","pages":"Article 100198"},"PeriodicalIF":0.0,"publicationDate":"2025-10-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145363234","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
A new ion source to perform deuterium ion beam-target surface fusion has been studied and designed. Analytical calculations including the Monte Carlo based simulation performed to estimate the energy and ion current necessary to produce up to 1010 n/s with solid targets. Frontiers of deuterium surface fusion yield on different metallic targets are calculated with a computational code. Planner ICP ion source selected to reach the estimated surface fusion yield. The secondary electron's trajectories are simulated for some different suppression potentials to reach the safe suppression with lowest possible spark problem. Theoretical analysis is performed to regulate the optimum distance between plasma and the accelerating electrodes to have parallel deuteron ion beam with necessary conditions to reach 108 n/s or further.
{"title":"Surface fusion in deuterium beam solid target reactions: A theoretical study on ion source","authors":"Alireza Asle Zaeem, Morteza Sedaghat Movahhed, Mirmohammadreza Seyedhabashi","doi":"10.1016/j.nucana.2025.100188","DOIUrl":"10.1016/j.nucana.2025.100188","url":null,"abstract":"<div><div>A new ion source to perform deuterium ion beam-target surface fusion has been studied and designed. Analytical calculations including the Monte Carlo based simulation performed to estimate the energy and ion current necessary to produce up to 10<sup>10</sup> n/s with solid targets. Frontiers of deuterium surface fusion yield on different metallic targets are calculated with a computational code. Planner ICP ion source selected to reach the estimated surface fusion yield. The secondary electron's trajectories are simulated for some different suppression potentials to reach the safe suppression with lowest possible spark problem. Theoretical analysis is performed to regulate the optimum distance between plasma and the accelerating electrodes to have parallel deuteron ion beam with necessary conditions to reach 10<sup>8</sup> n/s or further.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 4","pages":"Article 100188"},"PeriodicalIF":0.0,"publicationDate":"2025-09-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145121096","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-09-01DOI: 10.1016/j.nucana.2025.100184
L. Reddi Rani , N. Sowmya , H.C. Manjunatha , R.S. Susheela , M.M. Armstrong Arasu
We examined fusion cross-sections and fusion barrier distributions of 80 fusion reactions with Ca projectiles and targets in the atomic number range 76. The Wong formula was utilized to analyze the fusion cross-sections in which boundary conditions for the total potential were used to estimate the height and position of the fusion barrier. Five different proximity potentials such as Proximity 1977 [Annals of Physics 105, 427 (1977)], modified proximity 1977 [Nuclear Physics A 361, 117 (1981)], Bass 1977 [Physical Review Letters 39, 265 (1977)], Denisov proximity potential [Physics Letters B 526, 315 (2002)], and Ngo et al. [Nuclear Physics A 348, 140 (1980)] were taken into account while calculating the total potential. We found that Bass77 exhibits good agreement with that of the available experiments. To estimate the fusion barrier distributions, the Bass77 proximity potential-evaluated fusion cross-sections were employed. We determined the optimal fusion barrier distribution, , for each fusion reaction. We also explored the influence of entrance channel parameters on and discovered that is more systematic for the Coulomb interaction parameter. We also proposed an empirical equation for for Ca-induced fusion reactions leading to form compound nuclei 96 103.
{"title":"Role of entrance channel parameters on optimal incident energies in the formation of heavy nuclei using Ca-induced fusion reactions","authors":"L. Reddi Rani , N. Sowmya , H.C. Manjunatha , R.S. Susheela , M.M. Armstrong Arasu","doi":"10.1016/j.nucana.2025.100184","DOIUrl":"10.1016/j.nucana.2025.100184","url":null,"abstract":"<div><div>We examined fusion cross-sections and fusion barrier distributions of 80 fusion reactions with <span><math><msup><mspace></mspace><mrow><mn>40</mn><mo>,</mo><mn>48</mn></mrow></msup></math></span>Ca projectiles and targets in the atomic number range 76<span><math><mo>≤</mo><msub><mi>Z</mi><mi>T</mi></msub><mo>≤</mo><mn>93</mn></math></span>. The Wong formula was utilized to analyze the fusion cross-sections in which boundary conditions for the total potential were used to estimate the height and position of the fusion barrier. Five different proximity potentials such as Proximity 1977 [Annals of Physics 105, 427 (1977)], modified proximity 1977 [Nuclear Physics A 361, 117 (1981)], Bass 1977 [Physical Review Letters 39, 265 (1977)], Denisov proximity potential [Physics Letters B 526, 315 (2002)], and Ngo et al. [Nuclear Physics A 348, 140 (1980)] were taken into account while calculating the total potential. We found that Bass77 exhibits good agreement with that of the available experiments. To estimate the fusion barrier distributions, the Bass77 proximity potential-evaluated fusion cross-sections were employed. We determined the optimal fusion barrier distribution, <span><math><msup><mi>E</mi><mrow><mi>o</mi><mi>p</mi><mi>t</mi></mrow></msup></math></span>, for each fusion reaction. We also explored the influence of entrance channel parameters on <span><math><msup><mi>E</mi><mrow><mi>o</mi><mi>p</mi><mi>t</mi></mrow></msup></math></span> and discovered that <span><math><msup><mi>E</mi><mrow><mi>o</mi><mi>p</mi><mi>t</mi></mrow></msup></math></span> is more systematic for the Coulomb interaction parameter. We also proposed an empirical equation for <span><math><msup><mi>E</mi><mrow><mi>o</mi><mi>p</mi><mi>t</mi></mrow></msup></math></span> for <span><math><msup><mspace></mspace><mrow><mn>40</mn><mo>,</mo><mn>48</mn></mrow></msup></math></span>Ca-induced fusion reactions leading to form compound nuclei 96<span><math><mo>≤</mo><msub><mi>Z</mi><mi>c</mi></msub><mo>≤</mo></math></span> 103.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 3","pages":"Article 100184"},"PeriodicalIF":0.0,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145265596","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-09-01DOI: 10.1016/j.nucana.2025.100187
Leith Hani Rasheed , Muhanad Alrakabi , Ali Abid Abojassim
This study determined radiation dose rate (DR), annual effective dose (AED), and Excess Lifetime Cancer Risk (ELCR) due to background radiation in the soil of 12 cities in Al-Anbar governorate. The study used a portable dosimeter type RadEye PRD with a Geiger-Muller counter. One hundred and twenty-four locations were randomly selected from the study area from December 1, 2024 to January 1, 2025, determined using Global Positioning System (GPS). Also, the study used a Geographic Information System (GIS) software program to draw radiation maps in the study area. The results showed that the minimum value of radiation dose rate is 0.026 μSv/h in Kabisa city and the maximum was 0.119 μSv/h in Phosphate company, with an average value of 0.049±0.008 μSv/h. The range values for annual effective dose and excess lifetime cancer risk were 0.228 mSv/y - 1.046 mSv/y and 0.798×10−3-3.661×10−3, with average values of 0.431±0.077 and 1.509±0.270, respectively. The results of radiation dose rate and annual effective dose in all locations of the present study were within the average of the global average value according to the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) 2008 report, which is 0.247 μSv/hr and 2.4 mSv/y, respectively, except for two locations in the Phosphate area. Also, the average values of ELCR in all twelve cities in the Al-Anbar governorate were low, and they may be considered safe with respect to background radiation.
{"title":"Cancer risk due to background in soil samples of Al Anbar governorate, Iraq","authors":"Leith Hani Rasheed , Muhanad Alrakabi , Ali Abid Abojassim","doi":"10.1016/j.nucana.2025.100187","DOIUrl":"10.1016/j.nucana.2025.100187","url":null,"abstract":"<div><div>This study determined radiation dose rate (D<sub>R</sub>), annual effective dose (AED), and Excess Lifetime Cancer Risk (ELCR) due to background radiation in the soil of 12 cities in Al-Anbar governorate. The study used a portable dosimeter type RadEye PRD with a Geiger-Muller counter. One hundred and twenty-four locations were randomly selected from the study area from December 1, 2024 to January 1, 2025, determined using Global Positioning System (GPS). Also, the study used a Geographic Information System (GIS) software program to draw radiation maps in the study area. The results showed that the minimum value of radiation dose rate is 0.026 μSv/h in Kabisa city and the maximum was 0.119 μSv/h in Phosphate company, with an average value of 0.049±0.008 μSv/h. The range values for annual effective dose and excess lifetime cancer risk were 0.228 mSv/y - 1.046 mSv/y and 0.798×10<sup>−3</sup>-3.661×10<sup>−3</sup>, with average values of 0.431±0.077 and 1.509±0.270, respectively. The results of radiation dose rate and annual effective dose in all locations of the present study were within the average of the global average value according to the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) 2008 report, which is 0.247 μSv/hr and 2.4 mSv/y, respectively, except for two locations in the Phosphate area. Also, the average values of ELCR in all twelve cities in the Al-Anbar governorate were low, and they may be considered safe with respect to background radiation.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 3","pages":"Article 100187"},"PeriodicalIF":0.0,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145265597","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-09-01DOI: 10.1016/j.nucana.2025.100186
Mir Mohammad Reza Seyedhabashi , Maryam Ebrahimi , Darioush Rostamifard , Ehsanollah Noori , Ali Reza Asle Zaeem , Reza Goodarzi , Amir raeisdana
In this research, the diffusion of hydrogen atoms in the crystalline structure of tungsten was investigated using LAMMPS molecular dynamics simulation code. To describe the interatomic interactions of the W–H system, the EAM potential was used. Hydrogen atoms were placed in the tetrahedral sites of a perfect BCC tungsten lattice to simulate a realistic impurity distribution with a concentration of 2 %. Simulations were performed in a temperature range of 1400–2700K. After structure optimization, the Mean Squared Displacement (MSD) was calculated using the Einstein relation to determine the diffusion coefficients for each temperature. The results showed that with increasing temperature, the hydrogen diffusion coefficient increases exponentially and verifies the Arrhenius relationship. The effective activation energy parameter is calculated 1.48 eV, with a pre-exponential factor of 3.2×10−6m2/s. Physical analysis revealed three distinct diffusion regimes: at low temperatures, hydrogen mobility is limited by trapping effects; at intermediate temperatures, the TIS-TIS pathway is the dominant mechanism; and at high temperatures, the transition to TIS-OIS-TIS pathways is activated, leading to a sharp increase in the diffusion coefficient. The high value of the effective activation energy is attributed to the collective motion and interactions of the hydrogen atoms at this concentration. These results are applicable in predicting the behavior of tungsten under the high-temperature conditions of fusion reactors.
{"title":"Effect of temperature on hydrogen diffusion mechanism in tungsten: A molecular dynamics simulation study","authors":"Mir Mohammad Reza Seyedhabashi , Maryam Ebrahimi , Darioush Rostamifard , Ehsanollah Noori , Ali Reza Asle Zaeem , Reza Goodarzi , Amir raeisdana","doi":"10.1016/j.nucana.2025.100186","DOIUrl":"10.1016/j.nucana.2025.100186","url":null,"abstract":"<div><div>In this research, the diffusion of hydrogen atoms in the crystalline structure of tungsten was investigated using LAMMPS molecular dynamics simulation code. To describe the interatomic interactions of the W–H system, the EAM potential was used. Hydrogen atoms were placed in the tetrahedral sites of a perfect BCC tungsten lattice to simulate a realistic impurity distribution with a concentration of 2 %. Simulations were performed in a temperature range of 1400–2700K. After structure optimization, the Mean Squared Displacement (MSD) was calculated using the Einstein relation to determine the diffusion coefficients for each temperature. The results showed that with increasing temperature, the hydrogen diffusion coefficient increases exponentially and verifies the Arrhenius relationship. The effective activation energy parameter is calculated 1.48 eV, with a pre-exponential factor of 3.2×10<sup>−6</sup>m<sup>2</sup>/s. Physical analysis revealed three distinct diffusion regimes: at low temperatures, hydrogen mobility is limited by trapping effects; at intermediate temperatures, the TIS-TIS pathway is the dominant mechanism; and at high temperatures, the transition to TIS-OIS-TIS pathways is activated, leading to a sharp increase in the diffusion coefficient. The high value of the effective activation energy is attributed to the collective motion and interactions of the hydrogen atoms at this concentration. These results are applicable in predicting the behavior of tungsten under the high-temperature conditions of fusion reactors.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 3","pages":"Article 100186"},"PeriodicalIF":0.0,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145049662","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-08-14DOI: 10.1016/j.nucana.2025.100183
Mohamed S. El_Tokhy , Sergey Rozovs , Alexey Lubashevskiy , H. Kasban , Elsayed H. Ali
Gamma spectroscopy is a pivotal technique in radiation measurement and monitoring, with applications spanning nuclear physics, environmental science, and medical diagnostics. However, a major challenge in gamma spectroscopy is the dead time effect, which occurs when the detector is unable to register subsequent events while processing previous signals. This phenomenon leads to underestimation of true count rates and compromises the accuracy of spectral analysis. To overcome this limitation, we propose an efficient algorithm based on the Social Spider Optimization (SSO) technique to optimize dead time corrections and enhance the precision of count rate estimation. The SSO algorithm, inspired by the collective foraging behavior of social spiders, is employed to simultaneously optimize the Non-Paralyzable and paralyzable dead times, enabling accurate correction of observed count rates. By considering the complex interaction between multiple parameters, the algorithm provides a more precise correction compared to traditional methods. The performance of the proposed SSO-based algorithm is validated through experimental analysis and a direct comparison with literature-based results, demonstrating its superior accuracy and robustness. The experimental validation, conducted using a High-Purity Germanium (HPGe) detector, revealed significant improvements in the accuracy of count rate corrections. Specifically, the observed count rate, initially recorded at 10,007 counts per second, was corrected to 11,007.71 counts per second with an estimated dead time of 9.08 μs. This corrected count rate closely aligns with the true count rate, showing excellent agreement with literature-reported values.
{"title":"Optimization of dead time correction for digital gamma ray spectroscopy based on social spider algorithm","authors":"Mohamed S. El_Tokhy , Sergey Rozovs , Alexey Lubashevskiy , H. Kasban , Elsayed H. Ali","doi":"10.1016/j.nucana.2025.100183","DOIUrl":"10.1016/j.nucana.2025.100183","url":null,"abstract":"<div><div>Gamma spectroscopy is a pivotal technique in radiation measurement and monitoring, with applications spanning nuclear physics, environmental science, and medical diagnostics. However, a major challenge in gamma spectroscopy is the dead time effect, which occurs when the detector is unable to register subsequent events while processing previous signals. This phenomenon leads to underestimation of true count rates and compromises the accuracy of spectral analysis. To overcome this limitation, we propose an efficient algorithm based on the Social Spider Optimization (SSO) technique to optimize dead time corrections and enhance the precision of count rate estimation. The SSO algorithm, inspired by the collective foraging behavior of social spiders, is employed to simultaneously optimize the Non-Paralyzable and paralyzable dead times, enabling accurate correction of observed count rates. By considering the complex interaction between multiple parameters, the algorithm provides a more precise correction compared to traditional methods. The performance of the proposed SSO-based algorithm is validated through experimental analysis and a direct comparison with literature-based results, demonstrating its superior accuracy and robustness. The experimental validation, conducted using a High-Purity Germanium (HPGe) detector, revealed significant improvements in the accuracy of count rate corrections. Specifically, the observed count rate, initially recorded at 10,007 counts per second, was corrected to 11,007.71 counts per second with an estimated dead time of 9.08 μs. This corrected count rate closely aligns with the true count rate, showing excellent agreement with literature-reported values.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 3","pages":"Article 100183"},"PeriodicalIF":0.0,"publicationDate":"2025-08-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144865803","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-08-12DOI: 10.1016/j.nucana.2025.100182
Godwin K. Agbajor, Omamoke O.E. Enaroseha, Damaris Osiga-Aibangbee, Anita Franklin Akpolile, Aziakpono Blessing Umukoro
<div><div>In this study, measurements were made of the concentration of metals of heavy origin (Cd, Cr, Cu and Zn) and activity-characterized concentration of <sup>226</sup>Ra, <sup>232</sup>Th and <sup>40</sup>K in ten samples of local staple food (amala) that are accessible in Abraka by means of Atomic Absorption Spectrometry technique and Gamma ray spectrometry, respectively. Assessment was also made of possible carcinogenic risk for children and adults. Based on carcinogenic risk evaluation of the metals, the mean values of total average daily intake in mg/kg-day were 7.51984E-08 for Cd, 6.64596E-08 for Cr, 7.52187E-08 for Cu and 8.3785E-08 for Zn for children, while these values were 3.60862E-08 for Cd, 1.64861E-09 for Cr, 2.15744E-09 for Cu and 1.33517E-07 for Zn for adults. The average hazard quotients were 1.82202E-05 for Cd, 9.2564E-06 for Cr, 1.58334E-05 for Cu and 1.58604E-05 for Zn for children while these values were found to be 3.61706E-05 for Cd, 3.1181E-08 for Cr, 5.39351E-08 for Cu and 4.45056E-07 for Zn for adults. The average total hazard index were 5.46605E-05 for Cd, 2.77692E-05 for Cr, 4.75001E-05 for Cu and 4.75811E-05 for Zn for children and 2.96873E-05 for Cd, 1.50881E-05 for Cr, 2.57992E-05 for Cu and 2.58431E-05 for Zn for adults. The average cancer risk were 8.09253E-07 for Cd and 5.34189E-07 for Cr for children and 4.38597E-07 for Cd and 2.89519E-07 for Cr for adults. For Cu and Zn, no cancer risk was detected, for both children and adults.</div><div>The estimated radioactivity concentration for K-40, Ra-226 and Th-232 varied from 97.60 <span><math><mrow><mo>±</mo></mrow></math></span> 1.88 to 302.25<span><math><mrow><mo>±</mo></mrow></math></span> 0.43 Bqkg<sup>−1</sup> with a mean value of 236.67 <span><math><mrow><mo>±</mo></mrow></math></span> 1.07 and 15.18<span><math><mrow><mo>±</mo></mrow></math></span> 0.21 to 89.50<span><math><mrow><mo>±</mo></mrow></math></span> 1.83 Bqkg<sup>−1</sup> with a mean value of 42.89 <span><math><mrow><mo>±</mo></mrow></math></span> 1.10 as well as 39.40<span><math><mrow><mo>±</mo></mrow></math></span> 0.94 to 92.12<span><math><mrow><mo>±</mo></mrow></math></span> 0.94 Bqkg<sup>−1</sup> with a mean value of 65.45 <span><math><mrow><mo>±</mo></mrow></math></span> 1.71, respectively. The radioactivity levels of <sup>40</sup>K were found to be higher than those of <sup>226</sup>Ra and <sup>232</sup>Th for all samples. The calculated radium equivalent activities ranged from 103.09Bqkg<sup>−1</sup> to 235.22 Bqkg<sup>−1</sup> with an average value of 154.70 Bqkg<sup>−1</sup> and were found to be lower than the recommended value of 370 Bqkg<sup>−1</sup> by UNSCEAR. The absorbed possible dose rates were estimated to vary from the value of 46.70 nGyh<sup>−1</sup> to the value of 104.36 nGyh<sup>−1</sup> with an average value of 69.22 nGyh<sup>−1</sup>. The mean absorbed dose rates of the samples of amala in this study were also higher than the recommended average value of 55nGyh<sup>−1</s
{"title":"Ingestion exposure of natural radionuclide and toxic heavy metallic origin in samples of local staple food","authors":"Godwin K. Agbajor, Omamoke O.E. Enaroseha, Damaris Osiga-Aibangbee, Anita Franklin Akpolile, Aziakpono Blessing Umukoro","doi":"10.1016/j.nucana.2025.100182","DOIUrl":"10.1016/j.nucana.2025.100182","url":null,"abstract":"<div><div>In this study, measurements were made of the concentration of metals of heavy origin (Cd, Cr, Cu and Zn) and activity-characterized concentration of <sup>226</sup>Ra, <sup>232</sup>Th and <sup>40</sup>K in ten samples of local staple food (amala) that are accessible in Abraka by means of Atomic Absorption Spectrometry technique and Gamma ray spectrometry, respectively. Assessment was also made of possible carcinogenic risk for children and adults. Based on carcinogenic risk evaluation of the metals, the mean values of total average daily intake in mg/kg-day were 7.51984E-08 for Cd, 6.64596E-08 for Cr, 7.52187E-08 for Cu and 8.3785E-08 for Zn for children, while these values were 3.60862E-08 for Cd, 1.64861E-09 for Cr, 2.15744E-09 for Cu and 1.33517E-07 for Zn for adults. The average hazard quotients were 1.82202E-05 for Cd, 9.2564E-06 for Cr, 1.58334E-05 for Cu and 1.58604E-05 for Zn for children while these values were found to be 3.61706E-05 for Cd, 3.1181E-08 for Cr, 5.39351E-08 for Cu and 4.45056E-07 for Zn for adults. The average total hazard index were 5.46605E-05 for Cd, 2.77692E-05 for Cr, 4.75001E-05 for Cu and 4.75811E-05 for Zn for children and 2.96873E-05 for Cd, 1.50881E-05 for Cr, 2.57992E-05 for Cu and 2.58431E-05 for Zn for adults. The average cancer risk were 8.09253E-07 for Cd and 5.34189E-07 for Cr for children and 4.38597E-07 for Cd and 2.89519E-07 for Cr for adults. For Cu and Zn, no cancer risk was detected, for both children and adults.</div><div>The estimated radioactivity concentration for K-40, Ra-226 and Th-232 varied from 97.60 <span><math><mrow><mo>±</mo></mrow></math></span> 1.88 to 302.25<span><math><mrow><mo>±</mo></mrow></math></span> 0.43 Bqkg<sup>−1</sup> with a mean value of 236.67 <span><math><mrow><mo>±</mo></mrow></math></span> 1.07 and 15.18<span><math><mrow><mo>±</mo></mrow></math></span> 0.21 to 89.50<span><math><mrow><mo>±</mo></mrow></math></span> 1.83 Bqkg<sup>−1</sup> with a mean value of 42.89 <span><math><mrow><mo>±</mo></mrow></math></span> 1.10 as well as 39.40<span><math><mrow><mo>±</mo></mrow></math></span> 0.94 to 92.12<span><math><mrow><mo>±</mo></mrow></math></span> 0.94 Bqkg<sup>−1</sup> with a mean value of 65.45 <span><math><mrow><mo>±</mo></mrow></math></span> 1.71, respectively. The radioactivity levels of <sup>40</sup>K were found to be higher than those of <sup>226</sup>Ra and <sup>232</sup>Th for all samples. The calculated radium equivalent activities ranged from 103.09Bqkg<sup>−1</sup> to 235.22 Bqkg<sup>−1</sup> with an average value of 154.70 Bqkg<sup>−1</sup> and were found to be lower than the recommended value of 370 Bqkg<sup>−1</sup> by UNSCEAR. The absorbed possible dose rates were estimated to vary from the value of 46.70 nGyh<sup>−1</sup> to the value of 104.36 nGyh<sup>−1</sup> with an average value of 69.22 nGyh<sup>−1</sup>. The mean absorbed dose rates of the samples of amala in this study were also higher than the recommended average value of 55nGyh<sup>−1</s","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 3","pages":"Article 100182"},"PeriodicalIF":0.0,"publicationDate":"2025-08-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144893774","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-06-01DOI: 10.1016/j.nucana.2025.100174
Akorede O. Joledo , Muyiwa M. Orosun , Tarka Ademola
The concentration of radionuclides in produced water can vary significantly depending on the geological formations and the extraction techniques deployed in the production of oil and gas resources. Several factors such as water-rock interactions, reservoir age, and flow rates influence the mobility and concentration of radionuclides. High concentrations of radionuclides in produced water can pose potential risks to human health and the environment. This study combines laboratory measurements using Gamma Spectrometry and numerical modelling techniques to assess the concentration, and radiological impact of radionuclide exposure in samples of produced water collected from oil and gas production facilities. The mean activity concentrations of 238U and 232Th were 1.09 ± 0.17 Bq/l and 5.53 ± 0.36 Bq/l, respectively, while 40K was negligible. The radium equivalent activity (Raeq) in the produced water samples ranged from 1.53 Bq/l to 7.47 Bq/l, indicating a relatively low radiological hazard. This low radiological hazard was corroborated by the findings of the annual effective dose equivalent (AEDE) and other impact parameters. The Th/U ratios for the samples ranged from 3.00 to 40.30, suggesting varying levels of uranium and thorium content in the produced water samples. The significantly higher Th/U ratio in sample B suggests the presence of specific geological conditions favoring thorium retention, which may have radiological implications, particularly regarding radon gas emissions and associated health risks in confined spaces. The presence of 226Ra in location B indicates geological leaching, while the variations in 232Th and 238U concentrations reflect differences in local geology and hydrogeochemical processes. The absence of detectable 40K activity implies that potassium-rich mineral sources have limited influence on the produced water chemistry, although further analysis is needed to assess Potassium's overall geochemical contribution. These findings emphasize the need for continued monitoring and detailed geochemical assessments to better understand radionuclide mobility, potential contamination pathways, and their long-term environmental impact.
{"title":"Radiological impact assessment of produced water from oilfield production facilities in the Niger Delta region","authors":"Akorede O. Joledo , Muyiwa M. Orosun , Tarka Ademola","doi":"10.1016/j.nucana.2025.100174","DOIUrl":"10.1016/j.nucana.2025.100174","url":null,"abstract":"<div><div>The concentration of radionuclides in produced water can vary significantly depending on the geological formations and the extraction techniques deployed in the production of oil and gas resources. Several factors such as water-rock interactions, reservoir age, and flow rates influence the mobility and concentration of radionuclides. High concentrations of radionuclides in produced water can pose potential risks to human health and the environment. This study combines laboratory measurements using Gamma Spectrometry and numerical modelling techniques to assess the concentration, and radiological impact of radionuclide exposure in samples of produced water collected from oil and gas production facilities. The mean activity concentrations of <sup>238</sup>U and <sup>232</sup>Th were 1.09 ± 0.17 Bq/l and 5.53 ± 0.36 Bq/l, respectively, while <sup>40</sup>K was negligible. The radium equivalent activity (Ra<sub>eq</sub>) in the produced water samples ranged from 1.53 Bq/l to 7.47 Bq/l, indicating a relatively low radiological hazard. This low radiological hazard was corroborated by the findings of the annual effective dose equivalent (AEDE) and other impact parameters. The Th/U ratios for the samples ranged from 3.00 to 40.30, suggesting varying levels of uranium and thorium content in the produced water samples. The significantly higher Th/U ratio in sample B suggests the presence of specific geological conditions favoring thorium retention, which may have radiological implications, particularly regarding radon gas emissions and associated health risks in confined spaces. The presence of <sup>226</sup>Ra in location B indicates geological leaching, while the variations in <sup>232</sup>Th and <sup>238</sup>U concentrations reflect differences in local geology and hydrogeochemical processes. The absence of detectable <sup>40</sup>K activity implies that potassium-rich mineral sources have limited influence on the produced water chemistry, although further analysis is needed to assess Potassium's overall geochemical contribution. These findings emphasize the need for continued monitoring and detailed geochemical assessments to better understand radionuclide mobility, potential contamination pathways, and their long-term environmental impact.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 2","pages":"Article 100174"},"PeriodicalIF":0.0,"publicationDate":"2025-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144297691","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-04-08DOI: 10.1016/j.nucana.2025.100173
Xinxi Li , Bo Li , Yun Wang , Liang Chen , Xiaoling Xiong , Jie Chen , Lin Zou , Chaoqiang Huang , Dong Liu
Current work introduces a non-destructive testing method for evaluating the gas retention and internal pressure of sealed containers. Pulsed polychromatic neutrons of time-of-flight (TOF) neutron reflectometer Diting at the China Mianyang research reactor (CMRR) were utilized as the probe. By analyzing the transmitted neutron spectrum and employing an inversion fitting technique, the internal gas pressure with high accuracy up to 3 % can be determined. This method capitalizes on the large absorption cross-section of 3He gas, which provides the sensitivity required for detecting minute changes. The high intensity of the transmitted neutron beam enables rapid data collection, facilitating in situ measurement. The technique offers a direct measure of the gas pressure within sealed containers, which is significant for applications requiring quality control and safety measures, such as inertial confinement fusion (ICF) target pellet development and other non-destructive testing in various industries where the integrity and performance of sealed systems are paramount.
{"title":"A nondestructive method based on absorption of polychromatic neutron beam for monitoring internal gas of sealed container","authors":"Xinxi Li , Bo Li , Yun Wang , Liang Chen , Xiaoling Xiong , Jie Chen , Lin Zou , Chaoqiang Huang , Dong Liu","doi":"10.1016/j.nucana.2025.100173","DOIUrl":"10.1016/j.nucana.2025.100173","url":null,"abstract":"<div><div>Current work introduces a non-destructive testing method for evaluating the gas retention and internal pressure of sealed containers. Pulsed polychromatic neutrons of time-of-flight (TOF) neutron reflectometer <em>Diting</em> at the China Mianyang research reactor (CMRR) were utilized as the probe. By analyzing the transmitted neutron spectrum and employing an inversion fitting technique, the internal gas pressure with high accuracy up to 3 % can be determined. This method capitalizes on the large absorption cross-section of <sup>3</sup>He gas, which provides the sensitivity required for detecting minute changes. The high intensity of the transmitted neutron beam enables rapid data collection, facilitating in situ measurement. The technique offers a direct measure of the gas pressure within sealed containers, which is significant for applications requiring quality control and safety measures, such as inertial confinement fusion (ICF) target pellet development and other non-destructive testing in various industries where the integrity and performance of sealed systems are paramount.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 2","pages":"Article 100173"},"PeriodicalIF":0.0,"publicationDate":"2025-04-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143834908","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-04-03DOI: 10.1016/j.nucana.2025.100172
Mustapha Assalmi , Abdullah Alshreef , Sofia Jebbari , Assia Arectout , Pedro Arce , El Yamani Diaf
A novel approach involving quadrupole magnets has been proposed to deflect and disperse electrons in the irradiation fields, as well as a system for focusing beams at specific depths. This research also presents a comparison between VHEE and conventional radiotherapy, supported by the validation of our Monte Carlo simulations using real measurement data for low-energy electrons (6, 9 and 15 MeV) in water and air, thus ensuring the reliability of our results. Simulations demonstrate high accuracy, with agreement with measurement data of up to 0.58 % and less than 1.86 % for all validated energies and fields. The results show a significant reduction in entrance dose (82.4 %) with focused beams compared to unfocused beams, as well as a 17.6 % reduction at a depth of 30 cm. The study of the spread electron peak (SOEP) for 4 focused beams varies in magnetic field intensity to cover a depth of 11 cm–18 cm, with an entrance dose at a depth of 0.5 mm of 27.15 % and 24.5 % of the exit dose at a depth of 40 cm. The VHEEs also offer the advantage of low Linear Energy Transfer (LET) compared with protons, which reduces the risk of damage several times over.
提出了一种涉及四极磁体的新方法来偏转和分散辐射场中的电子，以及在特定深度聚焦光束的系统。本研究还比较了VHEE和传统放射治疗，并利用水和空气中低能电子（6,9和15 MeV）的实际测量数据验证了我们的蒙特卡罗模拟，从而确保了我们结果的可靠性。模拟结果表明，该方法具有较高的精度，与实测数据的符合率可达0.58%，与所有验证能量和场的符合率低于1.86%。结果表明，与未聚焦光束相比，聚焦光束的入口剂量显著降低（82.4%），在30 cm深度处降低了17.6%。研究了4束聚焦光束在11 cm ~ 18 cm范围内磁场强度变化时的展频电子峰（SOEP），在0.5 mm深度处的入口剂量为出口剂量的27.15%，在40 cm深度处为出口剂量的24.5%。与质子相比，VHEEs还具有低线性能量转移（LET）的优势，这将损坏的风险降低了几倍。
{"title":"A novel approach with quadrupole magnets for precise deflection, scattering and focusing of very high energy electron beams (VHEE)","authors":"Mustapha Assalmi , Abdullah Alshreef , Sofia Jebbari , Assia Arectout , Pedro Arce , El Yamani Diaf","doi":"10.1016/j.nucana.2025.100172","DOIUrl":"10.1016/j.nucana.2025.100172","url":null,"abstract":"<div><div>A novel approach involving quadrupole magnets has been proposed to deflect and disperse electrons in the irradiation fields, as well as a system for focusing beams at specific depths. This research also presents a comparison between VHEE and conventional radiotherapy, supported by the validation of our Monte Carlo simulations using real measurement data for low-energy electrons (6, 9 and 15 MeV) in water and air, thus ensuring the reliability of our results. Simulations demonstrate high accuracy, with agreement with measurement data of up to 0.58 % and less than 1.86 % for all validated energies and fields. The results show a significant reduction in entrance dose (82.4 %) with focused beams compared to unfocused beams, as well as a 17.6 % reduction at a depth of 30 cm. The study of the spread electron peak (SOEP) for 4 focused beams varies in magnetic field intensity to cover a depth of 11 cm–18 cm, with an entrance dose at a depth of 0.5 mm of 27.15 % and 24.5 % of the exit dose at a depth of 40 cm. The VHEEs also offer the advantage of low Linear Energy Transfer (LET) compared with protons, which reduces the risk of damage several times over.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 2","pages":"Article 100172"},"PeriodicalIF":0.0,"publicationDate":"2025-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143792732","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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