Nuclear Analysis最新文献

{"title":"Theoretical and experimental validation of dual rhenium radioisotope production for enhanced targeted cancer therapy","authors":"Ranjbar Hassan ,&nbsp;Bagheri Reza ,&nbsp;Janjani Iman","doi":"10.1016/j.nucana.2025.100202","DOIUrl":"10.1016/j.nucana.2025.100202","url":null,"abstract":"<div><h3>Objective</h3><div>For many years, different ligands have been combined with rhenium therapeutic radioisotopes, specifically rhenium-186 and 188, to create radiopharmaceuticals for the treatment of various illnesses. Because of the unique qualities that set each of these radioisotopes apart, they can all be used to eradicate different kinds of cancers. Large cancers can be effectively removed in 188Re thanks to the use of great-energy, long-distance beta particles. However, ¹⁸⁶Re's short range, low energy beta particles are a sufficient weapon to destroy tiny tumors with a high yield and little side effects. As a result, the properties of each of these radioisotopes can only partially address the therapy on their own. Therefore, we reasoned that ¹⁸⁸Re and ¹⁸⁶Re in conjunction must provide the greatest results when treating tumors of different sizes. One possible outcome of neutron-irradiation of natural rhenium is the simultaneous production of ¹⁸⁶Re and ¹⁸⁸Re.</div></div><div><h3>Methods</h3><div>We want to know if the natural irradiation of rhenium, together with the simultaneous synthesis of these radioisotopes, provides us with the right amounts of radioactivity to make compositional radiopharmaceuticals. This study examines the kind and quantity of impurities created, as well as the practical and theoretical evaluations of the simultaneous generation of ¹⁸⁸Re and ¹⁸⁶R to achieve compositional radiopharmaceuticals by neutron irradiation of natural rhenium in 5MWt pool-type light water research reactor.</div></div><div><h3>Results</h3><div>The outcomes demonstrated that the theoretical computations and experimental data correlate well. The data's greatest relative error has been determined to be 8 %.</div></div><div><h3>Conclusion</h3><div>The findings shown that ¹⁸⁶Re and ¹⁸⁸Re could be produced simultaneously with suitable and almost equal activities with irradiating natural rhenium for 100–120 h and considering 24 h for cooling. Also, the levels of impurities in the simultaneous manufacture of ¹⁸⁶Re and ¹⁸⁸Re using the neutron irradiation of natural rhenium are negligible in comparison to the primary products, and the primary products' activities are sufficient to make compositional radiopharmaceuticals.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 4","pages":"Article 100202"},"PeriodicalIF":0.0,"publicationDate":"2025-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145617979","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}

{"title":"Monte Carlo simulation of dose and residual activation in a polyethylene shuttle of the TRIGA Mark II reactor","authors":"Khalid Nabaoui ,&nbsp;Abdessamad Didi ,&nbsp;El Mehdi Alibrahmi ,&nbsp;Otmane Allaoui ,&nbsp;Jamila Yousfi ,&nbsp;El Mahjoub Chakir","doi":"10.1016/j.nucana.2025.100200","DOIUrl":"10.1016/j.nucana.2025.100200","url":null,"abstract":"<div><div>This study focuses on the use of polyethylene as the primary material for the fabrication of an irradiation shuttle intended for the TRIGA Mark II reactor. Designed to accommodate multiple sample capsules, the shuttle is subjected to prolonged neutron irradiation under real operating conditions. The objective is to analyze the interactions between thermal neutrons and polymeric materials in order to better understand their structural and radiological behavior under irradiation. The dose distribution was numerically modeled using the PHITS code, enabling precise identification of the regions of maximum intensity within the shuttle. The results provide a basis for optimizing the materials employed in nuclear environments, integrating radiological safety requirements with durability and mechanical performance.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 4","pages":"Article 100200"},"PeriodicalIF":0.0,"publicationDate":"2025-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145418219","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}

{"title":"Benchmarking of the efficiency of the NaI(Tl) detector using FLUKA, MCNP, and experimental measurements at multiple source distances","authors":"Zeenat Ullah ,&nbsp;Abdelhamid Jalil ,&nbsp;Xianpeng Yin ,&nbsp;Yingming Sang ,&nbsp;Javed Hussain ,&nbsp;Muhammad Shoaib ,&nbsp;Ghulam Hussan ,&nbsp;Da Chen","doi":"10.1016/j.nucana.2025.100185","DOIUrl":"10.1016/j.nucana.2025.100185","url":null,"abstract":"<div><div>Accurate calibration of NaI(Tl) scintillation detectors is essential for reliable gamma-ray spectrometry in nuclear safeguards and environmental radiation monitoring. This study investigates the full energy peak efficiency (FEPE) of a <span><math><msup><mn>2</mn><mrow><mi>′</mi><mi>′</mi></mrow></msup><mspace></mspace><mo>×</mo><mspace></mspace><msup><mn>2</mn><mrow><mi>′</mi><mi>′</mi></mrow></msup></math></span> NaI(Tl) detector using experimental measurements and Monte Carlo simulation performed with FLUKA and MCNP. Standard point sources (<span><math><mrow><msup><mrow></mrow><mrow><mn>133</mn></mrow></msup><mtext>Ba</mtext></mrow></math></span>, <span><math><mrow><msup><mrow></mrow><mrow><mn>137</mn></mrow></msup><mtext>Cs</mtext></mrow></math></span>, and <span><math><mrow><msup><mrow></mrow><mrow><mn>60</mn></mrow></msup><mtext>Co</mtext></mrow></math></span>) were measured at four source-detector distances (4, 8, 12, and 16 cm) covering photon energies from 356 to 1333 keV. Both simulation tools demonstrated an average deviation of less than 6 % and a maximum deviation of 18 % from the experimental results in all configurations. Furthermore, source misalignment was numerically evaluated and found to have a measurable impact only at short source-detector distance. This work represents the first integrated benchmarking of FLUKA and MCNP against experimental FEPE data across multiple geometries, offering a validated framework for accurate detector modeling and calibration.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 4","pages":"Article 100185"},"PeriodicalIF":0.0,"publicationDate":"2025-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145418218","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}

{"title":"Nano-sisal fiber reinforced polymer composites for biocompatible lightweight structural applications","authors":"V. Muthukumar ,&nbsp;D. Elil Raja ,&nbsp;P. Jayaprakash ,&nbsp;A. Suresh Babu","doi":"10.1016/j.nucana.2025.100199","DOIUrl":"10.1016/j.nucana.2025.100199","url":null,"abstract":"<div><div>This research focuses on the mechanical and thermal characterization of nano-sisal fiber-reinforced polymer composites, exploring the potential of incorporating nanomaterials to enhance the performance of traditional sisal fiber composites. Natural sisal fibers (NSF) serve as the starting point for the chemical and physical processes that produce sisal fibers. Several analytical techniques are used to describe the materials, such as Fourier transform infrared spectroscopy (FTIR), scanning electron microscopy (SEM), high-resolution transmission electron microscopy (HR-TEM), and field emission scanning electron microscopy (FE-SEM). This study investigates the synergistic effects of integrating nanoscale reinforcements into sisal fiber-reinforced polymer matrices. Mechanical properties, including tensile strength, flexural strength, and impact resistance, are systematically evaluated using standardized testing procedures. Fabricating epoxy polymer-based composites involves adding silver fibers in various weight percentages (1, 2, 3, 4, 5, 6, 7, and 8 %). The results highlight the influence of nanoscale additives on the overall mechanical performance and thermal stability of the composite materials. Furthermore, the study investigates the potential for improved load-bearing capacity, durability, flexural strength, tensile strength, impact resistance, thermal analysis, and heat resistance in sisal fiber composite samples, where these composites could exhibit utility. The findings of this research contribute to the understanding of nano-sisal fiber-reinforced polymer composites and their viability in various engineering applications.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 4","pages":"Article 100199"},"PeriodicalIF":0.0,"publicationDate":"2025-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145363235","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}

{"title":"Surface fusion in deuterium beam solid target reactions: A theoretical study on ion source","authors":"Alireza Asle Zaeem,&nbsp;Morteza Sedaghat Movahhed,&nbsp;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 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.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 4","pages":"Article 100188"},"PeriodicalIF":0.0,"publicationDate":"2025-12-01","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}

{"title":"Impact of P2O5 concentration on gamma-ray shielding in Na2O–B2O3-P2O5 glass","authors":"Issam Idrissi Janati ,&nbsp;Rodouan Touti ,&nbsp;Mohamed Naji ,&nbsp;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 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 (Z_eff) results indicated a higher probability of photon interaction with increased P₂O₅ content. The maximum Z_eff 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.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 4","pages":"Article 100198"},"PeriodicalIF":0.0,"publicationDate":"2025-12-01","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}

{"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 ,&nbsp;N. Sowmya ,&nbsp;H.C. Manjunatha ,&nbsp;R.S. Susheela ,&nbsp;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}

{"title":"Ingestion exposure of natural radionuclide and toxic heavy metallic origin in samples of local staple food","authors":"Godwin K. Agbajor,&nbsp;Omamoke O.E. Enaroseha,&nbsp;Damaris Osiga-Aibangbee,&nbsp;Anita Franklin Akpolile,&nbsp;Aziakpono Blessing Umukoro","doi":"10.1016/j.nucana.2025.100182","DOIUrl":"10.1016/j.nucana.2025.100182","url":null,"abstract":"&lt;div&gt;&lt;div&gt;In this study, measurements were made of the concentration of metals of heavy origin (Cd, Cr, Cu and Zn) and activity-characterized concentration of &lt;sup&gt;226&lt;/sup&gt;Ra, &lt;sup&gt;232&lt;/sup&gt;Th and &lt;sup&gt;40&lt;/sup&gt;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.&lt;/div&gt;&lt;div&gt;The estimated radioactivity concentration for K-40, Ra-226 and Th-232 varied from 97.60 &lt;span&gt;&lt;math&gt;&lt;mrow&gt;&lt;mo&gt;±&lt;/mo&gt;&lt;/mrow&gt;&lt;/math&gt;&lt;/span&gt; 1.88 to 302.25&lt;span&gt;&lt;math&gt;&lt;mrow&gt;&lt;mo&gt;±&lt;/mo&gt;&lt;/mrow&gt;&lt;/math&gt;&lt;/span&gt; 0.43 Bqkg&lt;sup&gt;−1&lt;/sup&gt; with a mean value of 236.67 &lt;span&gt;&lt;math&gt;&lt;mrow&gt;&lt;mo&gt;±&lt;/mo&gt;&lt;/mrow&gt;&lt;/math&gt;&lt;/span&gt; 1.07 and 15.18&lt;span&gt;&lt;math&gt;&lt;mrow&gt;&lt;mo&gt;±&lt;/mo&gt;&lt;/mrow&gt;&lt;/math&gt;&lt;/span&gt; 0.21 to 89.50&lt;span&gt;&lt;math&gt;&lt;mrow&gt;&lt;mo&gt;±&lt;/mo&gt;&lt;/mrow&gt;&lt;/math&gt;&lt;/span&gt; 1.83 Bqkg&lt;sup&gt;−1&lt;/sup&gt; with a mean value of 42.89 &lt;span&gt;&lt;math&gt;&lt;mrow&gt;&lt;mo&gt;±&lt;/mo&gt;&lt;/mrow&gt;&lt;/math&gt;&lt;/span&gt; 1.10 as well as 39.40&lt;span&gt;&lt;math&gt;&lt;mrow&gt;&lt;mo&gt;±&lt;/mo&gt;&lt;/mrow&gt;&lt;/math&gt;&lt;/span&gt; 0.94 to 92.12&lt;span&gt;&lt;math&gt;&lt;mrow&gt;&lt;mo&gt;±&lt;/mo&gt;&lt;/mrow&gt;&lt;/math&gt;&lt;/span&gt; 0.94 Bqkg&lt;sup&gt;−1&lt;/sup&gt; with a mean value of 65.45 &lt;span&gt;&lt;math&gt;&lt;mrow&gt;&lt;mo&gt;±&lt;/mo&gt;&lt;/mrow&gt;&lt;/math&gt;&lt;/span&gt; 1.71, respectively. The radioactivity levels of &lt;sup&gt;40&lt;/sup&gt;K were found to be higher than those of &lt;sup&gt;226&lt;/sup&gt;Ra and &lt;sup&gt;232&lt;/sup&gt;Th for all samples. The calculated radium equivalent activities ranged from 103.09Bqkg&lt;sup&gt;−1&lt;/sup&gt; to 235.22 Bqkg&lt;sup&gt;−1&lt;/sup&gt; with an average value of 154.70 Bqkg&lt;sup&gt;−1&lt;/sup&gt; and were found to be lower than the recommended value of 370 Bqkg&lt;sup&gt;−1&lt;/sup&gt; by UNSCEAR. The absorbed possible dose rates were estimated to vary from the value of 46.70 nGyh&lt;sup&gt;−1&lt;/sup&gt; to the value of 104.36 nGyh&lt;sup&gt;−1&lt;/sup&gt; with an average value of 69.22 nGyh&lt;sup&gt;−1&lt;/sup&gt;. The mean absorbed dose rates of the samples of amala in this study were also higher than the recommended average value of 55nGyh&lt;sup&gt;−1&lt;/s","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"4 3","pages":"Article 100182"},"PeriodicalIF":0.0,"publicationDate":"2025-09-01","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}

{"title":"Cancer risk due to background in soil samples of Al Anbar governorate, Iraq","authors":"Leith Hani Rasheed ,&nbsp;Muhanad Alrakabi ,&nbsp;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_R), 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.</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}

{"title":"Optimization of dead time correction for digital gamma ray spectroscopy based on social spider algorithm","authors":"Mohamed S. El_Tokhy ,&nbsp;Sergey Rozovs ,&nbsp;Alexey Lubashevskiy ,&nbsp;H. Kasban ,&nbsp;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":"2025-09-01","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}