Nuclear Engineering and Technology最新文献

{"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}

{"title":"Self-supervised denoising method for single neutron image based on the S2S-NR network","authors":"Wangtao Yu ,&nbsp;Peng Xu ,&nbsp;Xinghui Cai ,&nbsp;Man Zhou ,&nbsp;Jie Bao","doi":"10.1016/j.net.2025.103651","DOIUrl":"10.1016/j.net.2025.103651","url":null,"abstract":"<div><div>Fast neutron radiography technology has unique application advantages in the field of non-destructive testing. However, during the imaging process, the imaging system is inevitably affected by various factors, leading to significant noise contamination in the resulting neutron images, which affects subsequent processing and analysis. In recent years, self-supervised learning has become a powerful tool for single image denoising. We propose a self-supervised denoising method based on the Self2Self-Neutron Radiography (S2S-NR) network to remove noise from fast neutron images. We train the network using a single noisy fast neutron image, employ gated convolution for feature extraction, and perform dropout training on Bernoulli sampling instances of the neutron image. The results are estimated by averaging the predictions from various instances of the network with dropout. Furthermore, we incorporate no-reference image quality assessment metrics into the loss function to optimize the training process. Experimental results show that the method achieves state-of-the-art denoising performance on both simulated and real fast neutron images, demonstrating the effectiveness and practicality of this method as a potential solution for the denoising task in fast neutron imaging.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103651"},"PeriodicalIF":2.6,"publicationDate":"2025-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143911516","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":"Modeling and simulation of transient dose rate effect on power distribution networks of system-in-package","authors":"Yang Li ,&nbsp;Rong Lu ,&nbsp;Wenjun Li ,&nbsp;Dongwei Chen ,&nbsp;Ning Li ,&nbsp;Chaohui He ,&nbsp;Junlin Li ,&nbsp;Jinlei Wang ,&nbsp;Fangpei Li ,&nbsp;Guohe Zhang","doi":"10.1016/j.net.2025.103652","DOIUrl":"10.1016/j.net.2025.103652","url":null,"abstract":"<div><div>This paper investigates the transient dose rate effect (TDRE) on the power distribution networks (PDNs) of the SZ0501 system-in-package (SiP). Previous experimental results have revealed significant differences in failure thresholds between the SZ0501 SiP and its prototype printed circuit board (PCB).</div><div>To interpret these experimental findings, this study focuses on the PDNs of the SZ0501 SiP and develops optimized transient simulation models. Building on traditional Power Integrity (PI) and Signal Integrity (SI) co-simulation models, transient simulation models are developed by incorporating photocurrents into the PDNs. Transient simulations are conducted for both SiP and its prototype PCB under three conditions, including non-radiation, short- or long-pulse photocurrent injections, single- or multi-pulse photocurrent injections, especially considering the coupling effect in the multiple injection case. Simulation results indicate the power supply noise induced by transient photocurrents is obvious and considerably impacts the power supply stability. A comparison with the previous experimental data reveals that the prototype PCB possessing independent PDNs demonstrates greater stability under transient γ irradiation than the SiP with shared PDNs. This study underscores the importance of considering PDNs in the design of miniaturized systems to enhance the system reliability in transient radiation environments.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103652"},"PeriodicalIF":2.6,"publicationDate":"2025-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143900144","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":"Evaluating shelter suitability during nuclear accidents using the TOPSIS multi-criteria decision-making method","authors":"Han Young Joo,&nbsp;Joo Hyun Moon","doi":"10.1016/j.net.2025.103648","DOIUrl":"10.1016/j.net.2025.103648","url":null,"abstract":"<div><div>This study presents a comprehensive evaluation of the suitability of administrative districts containing designated evacuation shelters in the Busan and Ulsan metropolitan regions, near the Kori, Saeul, and Wolsong Nuclear Power Plants (NPPs) in the Republic of Korea. Using the Technique for Order of Preference by Similarity to Ideal Solution (TOPSIS) method, the analysis incorporates key criteria such as proximity to NPPs, shelter capacity relative to population, and risk factors associated with wind direction. Population data, shelter locations, and five years of meteorological records were integrated to assess district suitability under varying seasonal and time-of-day conditions. The study highlights the significant role of dynamic meteorological factors in influencing the dispersion patterns of radioactive materials and emphasizes the necessity of incorporating these factors into district evaluations. The results identify the most suitable administrative districts for shelter placement, offering valuable insights for strengthening nuclear disaster preparedness and emergency response strategies. Additionally, the findings provide a foundation for local governments to enhance shelter safety and accessibility through strategic planning. This study demonstrates the importance of integrating environmental factors and capacity planning into district assessments, ultimately contributing to improved public safety and resilience in the event of a nuclear accident.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103648"},"PeriodicalIF":2.6,"publicationDate":"2025-04-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143907051","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":"Comparative analysis of VVER-1200 core inventory considering non-uniform and uniform reactor core power distribution","authors":"Md Rosaidul Mawla ,&nbsp;Anisur Rahman ,&nbsp;Md. Shafiqul Islam","doi":"10.1016/j.net.2025.103635","DOIUrl":"10.1016/j.net.2025.103635","url":null,"abstract":"<div><div>The impact of reactor core power distribution on radionuclide inventory calculations in the VVER-1200 reactor was analyzed using the ORIGEN, focusing on 135 radionuclides categorized into seven groups. The study considers two core models: one utilizing the dual enrichment strategy (4.4 % and 4.9 %, averaging 4.68 %) and another with a uniform enrichment of 4.79 %. Under non-uniform power distribution, activation product activity is calculated as 2.252 × 10¹⁸ Bq for the mixed enrichment (4.4 % &amp; 4.9 %) and 2.229 × 10¹⁸ Bq for the uniform 4.79 % enrichment. Under uniform power distribution, these values are 2.364 × 10¹⁸ Bq and 2.193 × 10¹⁸ Bq, respectively. Similarly, actinides and their daughters exhibit total activities of 8.279 × 10¹⁹ Bq and 8.190 × 10¹⁹ Bq under non-uniform power, compared to 8.662 × 10¹⁹ Bq and 8.003 × 10¹⁹ Bq under uniform power. Fission products dominate the radionuclide inventory, with total activities of 3.895 × 10²⁰ Bq and 3.893 × 10²⁰ Bq in non-uniform scenarios, versus 3.830 × 10²⁰ Bq and 3.826 × 10²⁰ Bq in uniform scenarios. Although the overall radionuclide inventory difference between uniform and non-uniform distributions is minimal, localized regions in non-uniform distributions exhibit higher activity due to high burnup. These findings are crucial for accident analysis, safety assessment, radioactive waste management, and the decommissioning of nuclear facilities.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103635"},"PeriodicalIF":2.6,"publicationDate":"2025-04-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143825907","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}