Nuclear Engineering and Technology最新文献

{"title":"Organ doses for monkey anatomy models with different postures exposed to external photons","authors":"Jae W. Jung ,&nbsp;Daniel D. Lee ,&nbsp;Ae-Kyoung Lee ,&nbsp;Hyung-Do Choi","doi":"10.1016/j.net.2025.103603","DOIUrl":"10.1016/j.net.2025.103603","url":null,"abstract":"<div><h3>Background</h3><div>Understanding how external radiation from nuclear accidents or radiological attacks affects internal human anatomy is essential to accurately assess health risks and develop effective treatments. we calculated a library of organ dose conversion coefficients for anatomical monkey models in a standing, crawling, and squatting postures for the first time by using Monte Carlo radiation transport methods combined with anatomical monkey models.</div></div><div><h3>Methods</h3><div>We adopted previously published anatomical monkey models with three different postures: crawling, squatting, and standing. Radiation doses to a total of 39 organs and tissues were calculated using a general-purpose Monte Carlo radiation transport code, MCNP6.2, for the photon fields with 33 mono-energy bins ranging from 0.01 to 20 MeV in six different irradiation geometries: antero-posterior (AP), postero-anterior (PA), left lateral (LLAT), right lateral (RLAT), rotational (ROT), and isotropic (ISO).</div></div><div><h3>Results</h3><div>We found that the dose conversion coefficients derived from the standing posture may overestimate organ dose by up to 13-fold compared to the crawling position (e.g., large intestine in AP irradiation geometry). Irradiation geometry has the most substantial impact on organ doses in the crawling posture compared to squatting and standing postures. Average coefficients of variation over different organs were 51 % in crawling posture compared to 16 % and 17 % for standing and squatting postures, respectively.</div></div><div><h3>Conclusion</h3><div>In the present research, we employed the Monte Carlo radiation transport techniques to develop a library of organ dose conversion coefficients for an anatomical monkey model considering various postures and six distinct irradiation geometries. We found that the existing dose conversion coefficients for the standing posture may substantially overestimate organ doses for monkeys in more natural postures. Our data should be useful for understanding the impact of radiation events to human anatomy by evaluating the impact on monkey's anatomy as a surrogate.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103603"},"PeriodicalIF":2.6,"publicationDate":"2025-04-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143851615","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Time-of-flight based one-dimensional position estimation of radioactive sources using artificial neural network model","authors":"Jinhong Kim ,&nbsp;Siwon Song ,&nbsp;Jae Hyung Park ,&nbsp;Seunghyeon Kim ,&nbsp;Sangjun Lee ,&nbsp;Seung Hyun Cho ,&nbsp;Cheolhaeng Huh ,&nbsp;Bongsoo Lee","doi":"10.1016/j.net.2025.103662","DOIUrl":"10.1016/j.net.2025.103662","url":null,"abstract":"<div><div>This study presents a novel approach for one-dimensional gamma ray source position estimation by integrating plastic scintillating fiber technology, time-of-flight (ToF) measurements, and artificial neural network (ANN) techniques. The methodology employs a systematic signal processing framework consisting of constant fraction discrimination (CFD) for precise timing extraction, amplitude-based filtering for noise reduction, and statistical analysis of ToF data to enhance measurement consistency. A two-stage ANN architecture was developed incorporating dual hidden layers with ReLU activation functions and weighted correction factors to optimize spatial localization performance. The system was experimentally validated using a Cs-137 radiation source across a 10-m measurement range with data collected at both regular intervals and random positions to assess interpolation capabilities. Comparative analysis between the ANN-based approach and theoretical calculations demonstrated a 90.17 % enhancement in position estimation precision, achieving an average error of 0.0225 m compared to 0.2289 m with conventional methods. Standard deviations in position estimates remained consistently below 0.1 m across the operational range, indicating robust performance stability. These results substantiate that combining sophisticated timing measurements with machine learning strategies advances radiation detection systems applicable to environmental monitoring, nuclear safety protocols, and emergency response scenarios.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103662"},"PeriodicalIF":2.6,"publicationDate":"2025-04-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143874204","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Investigation of shielding properties and mechanisms of boron-containing magnesium-rich tailings for nuclear shielding application","authors":"Mengge Dong ,&nbsp;G. Lakshminarayana ,&nbsp;Xuefei Zhang ,&nbsp;Xiangxin Xue","doi":"10.1016/j.net.2025.103660","DOIUrl":"10.1016/j.net.2025.103660","url":null,"abstract":"<div><div>Efficient utilization of boron-containing magnesium-rich tailings (BCMRTs) represents a critical challenge for the sustainable development of boron industry. This study introduces an innovative approach to repurpose BCMRTs as shielding materials and systematically investigates their shielding properties and underlying mechanisms against thermal/fast neutrons, and gamma rays. The findings demonstrate that BCMRTs exhibit exceptional thermal neutron attenuation, achieving a shielding efficiency of up to 100 % with merely 1 cm of material, thereby surpassing the performance of certain commercially available shields. However, further optimization is necessary to enhance their efficiency against fast neutrons and gamma rays. Neutron attenuation mechanism is predominantly governed by absorption effect of boron in low-energy range, elements with higher atomic number contribute in middle energy range through elastic scattering, and both elastic and inelastic scattering in high energy range. Gamma ray attenuation mechanism is predominantly governed by elements with high atomic number, with distinct nuclear interactions dominating across various energy ranges. Furthermore, comprehensive attenuation parameters for both narrow-beam and wide-beam gamma rays within the 0.001–100,000 MeV range are presented. This research provides critical insights into the potential application of BCMRTs in the development of advanced shielding materials.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103660"},"PeriodicalIF":2.6,"publicationDate":"2025-04-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143863643","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Optimization of a water-intake system for monitoring radionuclides in aquatic environments","authors":"Dayeong Lee ,&nbsp;Seongjin Maeng ,&nbsp;Sang Hoon Lee","doi":"10.1016/j.net.2025.103656","DOIUrl":"10.1016/j.net.2025.103656","url":null,"abstract":"<div><div>We designed and characterized a water-intake radiation monitoring system using a 3\" × 3″ NaI(Tl) detector for real-time monitoring of, for example, nuclear power plant radioactive effluents. The MCNP6 code was used to determine the optimized container size and detector position for homogeneous ¹³¹I and ¹³⁷Cs volumetric sources. Based on the simulation results, the dimensions of the monitoring system were determined. The simulation model was initially verified by comparison with the measurement results of a paper filter certified reference materials in water. Subsequently, it was further validated by comparison with the detection efficiency for ⁴⁰K in a KCl volumetric source measurement experiment, which confirmed that the detection efficiency well matched experimental data for volumetric sources. Using the validated simulation model, the detection efficiency of ¹³¹I and ¹³⁷Cs volumetric sources in a water-filled container was assessed. To consider background radioactivity, three types of water samples—freshwater, brackish water, and seawater—were experimentally measured. Based on these measurements, the minimum detectable activity for ¹³¹I and ¹³⁷Cs volumetric sources was determined for each of the three water sample types.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103656"},"PeriodicalIF":2.6,"publicationDate":"2025-04-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143859739","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Adjustment of reactor pressure vessel embrittlement trend curves using a mixed-effects model","authors":"Gyeong-Geun Lee,&nbsp;Bong-Sang Lee,&nbsp;Min-Chul Kim,&nbsp;Junhyun Kwon,&nbsp;Jong-Min Kim","doi":"10.1016/j.net.2025.103654","DOIUrl":"10.1016/j.net.2025.103654","url":null,"abstract":"<div><div>This study presents a novel approach for adjusting the generic reactor pressure vessel embrittlement trend curve (ETC), ASTM E900-15, using a mixed-effects model based on Baseline22, a compiled dataset of surveillance test data from nuclear power plants worldwide. Using this statistical framework, systematic deviations owing to initial material properties, notch orientations, and other plant-specific factors were separated from measurement errors, providing a more accurate assessment of embrittlement trends. Two types of adjustment models were explored: an intercept-only model (AM3) and a combined intercept-slope model (AM6). The AM3 model, which estimates only group-specific intercepts, effectively reduces prediction errors compared to ASTM E900-15 model while maintaining interpretability and simplicity, making it particularly suitable for regulatory applications. AM6, which incorporates group-specific slopes and covariance terms, further improves predictive accuracy, but introduces estimation complexities, so its suitability for conservate regulatory applications requires further discussion. To facilitate the practical implementation of AM3, closed-form expressions for group-specific intercept adjustments were derived, enabling the estimation of adjustment factors without the need for Bayesian Markov chain Monte Carlo models or complex statistical tools. Additionally, the standard deviations of the intercept means and prediction intervals were formulated as functions of the group size, providing a straightforward method for assessing embrittlement trends as new surveillance test results became available. This study demonstrates that existing generic ETC models can be dynamically refined and updated using plant-specific surveillance test data, while maintaining robustness and regulatory applicability. These findings lay the groundwork for the future refinement of standard ETC models, potential integration with regulatory frameworks, and improved long-term integrity assessments of reactor pressure vessels in aging nuclear power plants.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103654"},"PeriodicalIF":2.6,"publicationDate":"2025-04-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143874255","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Optimization of operating conditions for Gamma Emission Tomography to improve partial-defect detection accuracy within PWR-type spent nuclear fuel","authors":"Hyung-Joo Choi ,&nbsp;Hyun Joon Choi ,&nbsp;Hyun Cheol Lee ,&nbsp;Yong Hyun Chung ,&nbsp;Chul Hee Min","doi":"10.1016/j.net.2025.103644","DOIUrl":"10.1016/j.net.2025.103644","url":null,"abstract":"<div><div>The Spent Nuclear Fuel (SNF) contains a variety of nuclear material that can be diverted for military purposes and unauthorized proliferation. To ensure safety management and non-proliferation of SNF, an effective inspection method, such as Gamma Emission Tomography (GET) is necessary. In the previous study, the Yonsei Single-photon Emission Computed Tomography (YSECT) instrument was proposed and developed. To improve inspection accuracy in the central region containing the high-density SNF rod, the operating conditions, such as energy window and rotation interval, of the YSECT instrument are optimized in this study. The tomographic images were obtained under various operating conditions, and each condition was optimized by evaluating the quality of the tomographic image. Based on the results, the optimal energy window and rotation interval were determined to be 1274 keV region and 1-degree, respectively. The Signal-to-Noise Ratio (SNR) was improved 1.32-fold with optimized energy window compared to conventional energy window (6.98 of SNR for 662 keV region). Also, the streak artifact was reduced through the application of the optimized rotation interval. These optimized conditions improved inspection accuracy for partial-defect detection. In the future, the experimental study with the mock-up of SNF and pool will be conducted to validate the optimized operating conditions.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103644"},"PeriodicalIF":2.6,"publicationDate":"2025-04-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143842536","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Investigation of optical and radiation shielding properties in bismuth oxide-doped barium borate glasses","authors":"Mohammad H. Alhakami ,&nbsp;A.S. Abouhaswa ,&nbsp;Numa A. Althubiti ,&nbsp;Taha Abdel Mohaymen Taha","doi":"10.1016/j.net.2025.103633","DOIUrl":"10.1016/j.net.2025.103633","url":null,"abstract":"<div><div>This study presents a novel exploration of barium borate glasses doped with bismuth oxide (Bi₂O₃) to simultaneously enhance their optical and radiation shielding properties. Using a melting-quenching technique, a series of glasses with compositions of (65-x)B₂O₃ + 5WO₃ + 20BaO + 10Na₂O + xBi₂O₃ (where x = 0, 5, 10, 15, and 20 mol%) was produced. X-ray diffraction analysis (XRD) confirmed the amorphous nature of the samples, while Fourier-transform infrared spectroscopy (FTIR) revealed the conversion of trigonal [BO₃] to tetrahedral [BO₄] units in the glass structure. The incorporation of Bi₂O₃ led to a significant increase in density and molar volume. The optical band gap decreased from 3.96 eV to 3.30 eV with higher Bi₂O₃ concentrations. Notably, the refractive index also increased from 1.49 to 1.63 with the addition of Bi₂O₃. The elastic moduli (Young's modulus, shear modulus, and bulk modulus) decreased with increasing Bi₂O₃ content. Additionally, the analysis of radiation shielding effectiveness demonstrated that Bi₂O₃ significantly increased both the mass attenuation coefficient (MAC) and linear attenuation coefficient (LAC), particularly for low-energy photon interactions, making these glasses suitable for applications involving gamma and X-ray radiation protection. The results establish the potential of Bi₂O₃-doped barium borate glasses as advanced materials for radiation shielding, photonic devices, and other optoelectronic applications.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103633"},"PeriodicalIF":2.6,"publicationDate":"2025-04-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143842537","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Development of robust nuclear safeguards methods for gas centrifuge enrichment plants","authors":"Donghyeok Koo ,&nbsp;Junyoung Seo ,&nbsp;Seung Min Woo ,&nbsp;Byeongjun Kim ,&nbsp;Kyunam Kim ,&nbsp;Eunju Jun ,&nbsp;Soon Heung Chang","doi":"10.1016/j.net.2025.103653","DOIUrl":"10.1016/j.net.2025.103653","url":null,"abstract":"<div><div>The role of nuclear energy in reducing carbon emissions has becomes increasingly significant with the intensifying climate crisis. The supply of nuclear fuels, particularly high-assay low-enriched uranium, has gained prominence with the growing demand for nuclear energy. However, the development of this technology has been challenged by proliferation risks associated with enrichment facilities. Expanding nuclear energy while securing robust nonproliferation measures is essential for maximizing the potential of nuclear energy while ensuring its peaceful application. This study proposes advanced safeguards for gas centrifuge enrichment plants for mitigating these risks and enhancing the benefits of nuclear energy. This paper introduces eight measures, including the implementation of a remote shutdown system and an off-grid power system, which are advanced safeguards that have not been utilized previously. In addition, new convergence technologies such as the instrumentation cross-verification system, digital twin real-time nuclear material control and accounting system, and remotely piloted quasi-inspection drone robot were introduced for enhancing the safeguards. Further, enhanced verification, increased sample sizes, and resident inspectors aim to rigorously enforce the existing safeguards. When implemented in a coordinated manner, these safeguard measures have the potential to enhance proliferation resistance in uranium enrichment plants while promoting their peaceful use.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103653"},"PeriodicalIF":2.6,"publicationDate":"2025-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143868811","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Development of a MOC-based multiphysics coupling method for analysis of FCM-fueled micro gas-cooled reactor","authors":"Kuaiyuan Feng ,&nbsp;Qufei Song ,&nbsp;Yihu Wang ,&nbsp;Hui Guo ,&nbsp;Tenglong Cong ,&nbsp;Yao Xiao ,&nbsp;Hanyang Gu","doi":"10.1016/j.net.2025.103645","DOIUrl":"10.1016/j.net.2025.103645","url":null,"abstract":"<div><div>At present, Fully Ceramic Microencapsulated (FCM) fuel with randomly dispersed tri-structural isotropic (TRISO) particles is widely used in gas-cooled microreactors. Gas-cooled microreactors usually exhibit limited volume and complex structure, with tightly coupled multi-physical fields inside the core, presenting challenges for multiphysics analysis. In this work, a MOC-based multiphysics coupling method for analysis of FCM-fueled micro gas-cooled reactor within the Multiphysics Object-Oriented Simulation Environment (MOOSE) framework is developed and verified. The fuel assembly calculation results show that the generated multi-group cross-section (MGXS) at different temperature points exhibits high computational accuracy. The MOC-MOOSE results exhibit a high computational accuracy in <em>k</em>_<em>eff</em>, power distribution, and temperature field. Meanwhile, the calculation cost for the MOC-MOOSE method is only 10 % of that required by the benchmark solver, demonstrating high computational efficiency. At last, the full-core multiphysics coupling was conducted. The three-dimensional pin-by-pin fuel power distribution was obtained, with the highest power occurring in the outermost fuel rods of the peripheral fuel assemblies at the middle plane of the axial active region. The maximum fuel, matrix, and coolant temperatures are 1698 K, 1206 K, and 1002 K, separately.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103645"},"PeriodicalIF":2.6,"publicationDate":"2025-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143868812","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Stringent environmental policies: How they shape the future of nuclear energy generation","authors":"Chuan Zhang ,&nbsp;Mian Gohar Rahman Zafar ,&nbsp;Francis Gaudreault ,&nbsp;Ousama Ben-Salha ,&nbsp;Adeeb Alhebri","doi":"10.1016/j.net.2025.103650","DOIUrl":"10.1016/j.net.2025.103650","url":null,"abstract":"<div><div>Nuclear energy is a low-carbon energy source that can replace fossil fuels in the energy mix. However, the serious risks associated with nuclear energy generation must be effectively managed. Environmental policy stringency can counter these risks by compelling the polluted firms and industries to switch to clean energy sources, thereby enhancing the production of alternative and clean energy sources, including nuclear energy. Empirical evidence in this context is missing, confirming a gap in the nuclear energy literature. In order to plug this gap, this research examines how stringent environmental policies can enhance nuclear energy generation in the leading 18 nuclear energy-producing nations from 1995 to 2021. In order to examine the empirical connection between environmental policy and nuclear energy generation, we employ the CS-ARDL model. The results indicate that stringent environmental policies lead to a decline in long-term nuclear energy generation. Nonetheless, the environmental policy does not affect short-term nuclear energy generation. Moreover, environmental technology, financial advancement, and sustainable development significantly enhance long-term nuclear energy generation. In the short term, all these variables do not substantially affect nuclear energy generation except environmental technology, which improves nuclear energy generation. Given the significance of environmental policy stringency for nuclear energy production, we suggest that the government needs to implement strict environmental policies with a special focus on the energy sector.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103650"},"PeriodicalIF":2.6,"publicationDate":"2025-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143868810","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}