Nuclear Engineering and Technology最新文献

{"title":"Burnup dynamics and reactivity change in proton induced Tc-99 transmutation fuel assembly","authors":"Chang M. Kang ,&nbsp;Youngin Kim","doi":"10.1016/j.net.2025.103520","DOIUrl":"10.1016/j.net.2025.103520","url":null,"abstract":"<div><div>Neutron transmutation presents a viable method for the management and disposal of long-lived fission products. A newly published method describes a transmutation system that utilizes proton spallation in conjunction with a subcritical fuel assembly. This innovative approach has demonstrated the ability to reduce the transmutation half-life of technetium-99 (Tc-99) to less than one year. This study investigates the impact of Tc-99 concentrations on the subcriticality of the transmutation device during burnup using the Serpent 2 Monte Carlo neutron transport code. The burnup simulation demonstrates that (1) The number densities of U-235 and Tc-99 decrease steadily across all cases as burnup extends up to 600 days, (2) k_eff decreases steadily and remains below 1.0 after 600 days of burnup. Specifically, k_eff is below 0.7 in UO₂ fuels and below 0.1 in UF₄ fuels after 600 days. These findings provide valuable insights into optimizing and ensuring the safety of the transmutation device.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 7","pages":"Article 103520"},"PeriodicalIF":2.6,"publicationDate":"2025-02-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143681758","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Corrigendum to “High-fidelity numerical investigation on structural integrity of SFR fuel cladding during design basis events” [NET56 (2024) p.359-374]","authors":"Seo-Yoon Choi ,&nbsp;Hyung-Kyu Kim ,&nbsp;Min-Seop Song ,&nbsp;Jae-Ho Jeong","doi":"10.1016/j.net.2025.103501","DOIUrl":"10.1016/j.net.2025.103501","url":null,"abstract":"","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 2","pages":"Article 103501"},"PeriodicalIF":2.6,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143099595","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Validation of the FLUKA code to simulate response functions of organic liquid scintillator for high‐energy neutrons","authors":"Ahad Ghavami,&nbsp;Mojtaba Tajik","doi":"10.1016/j.net.2024.09.001","DOIUrl":"10.1016/j.net.2024.09.001","url":null,"abstract":"<div><div>In this research, the FLUKA code was employed to calculate the response functions of the BC501A organic scintillation detector for energies ranging from 25 to 800 MeV. Using the AUXSCORE, EVENTBIN and TCQUENCH cards, the response function of the BC501A organic scintillation detector to mono-energetic neutrons in the energy range of 25–800 MeV was computed. The comparison confirms that the simulation results obtained from the FLUKA code show a promising agreement with the results obtained from experiments, other codes, and the analytical method.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 2","pages":"Article 103198"},"PeriodicalIF":2.6,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143099598","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Localizing multiple radiation sources actively with a particle filter","authors":"Tomas Lazna,&nbsp;Ludek Zalud","doi":"10.1016/j.net.2024.08.040","DOIUrl":"10.1016/j.net.2024.08.040","url":null,"abstract":"<div><div>We discuss the localization of radiation sources whose number and other relevant parameters are not known in advance. The data collection is ensured by an autonomous mobile robot that performs a survey in a defined region of interest populated with static obstacles. The measurement trajectory is information-driven rather than pre-planned, and the localization exploits a regularized particle filter estimating the sources’ parameters continuously. Regarding the dynamic robot control, this switches between two modes, one attempting to minimize the Shannon entropy and the other aiming to reduce the variance of expected measurements in unexplored parts of the target area; both of the modes maintain safe clearance from the obstacles. The performance of the algorithms was tested in a simulation study based on real-world data acquired previously from three radiation sources exhibiting various activities. Our approach reduces the time necessary to explore the region and to find the sources by approximately 40 %; at present, however, the method is unable to reliably localize sources that have a relatively low intensity. In this context, additional research has been planned to increase the credibility and robustness of the procedure and to improve the robotic platform autonomy.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 2","pages":"Article 103171"},"PeriodicalIF":2.6,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143099956","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Development of a force identification method using system-level measurements with component-level reduced-order modeling","authors":"Hyeongyeong Jin,&nbsp;Seunghun Baek","doi":"10.1016/j.net.2025.103503","DOIUrl":"10.1016/j.net.2025.103503","url":null,"abstract":"<div><div>The accurate estimation of excitation forces is essential for maintaining the structural integrity of dynamic systems. However, direct measurement of excitation forces is often infeasible in practical scenarios. To address this challenge, indirect measurement techniques have been the focus of significant research efforts. This study introduces a novel methodology for indirectly estimating excitation forces using the Component Mode Synthesis (CMS) technique. The proposed approach calculates excitation forces through equations of motion derived from a reduced-order model based on CMS. By utilizing system-level response data obtained from a minimal number of measurement points, this method achieves high prediction accuracy while substantially reducing computational demands. Validation of the proposed approach was performed through both Finite Element Method (FEM)-based simulations and experimental testing under various conditions. The results demonstrated the method’s robustness and accuracy, confirming its effectiveness in estimating excitation forces. This research provides a practical and efficient framework for force identification in dynamic systems, with broad potential for application across diverse industrial sectors.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 7","pages":"Article 103503"},"PeriodicalIF":2.6,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143681670","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Study on radiation protection for isotope production facility with 100 MeV proton beam","authors":"Chen Li ,&nbsp;Ya-Ling Zhang ,&nbsp;Zheng Wei ,&nbsp;Wei Wang ,&nbsp;Xue-Zhi Zhang ,&nbsp;Ji-Zheng Duan ,&nbsp;Lei Yang","doi":"10.1016/j.net.2025.103519","DOIUrl":"10.1016/j.net.2025.103519","url":null,"abstract":"<div><div>The Precision Radiotherapy α-Isotope R&amp;D Platform in Gansu Province aims to produce several alpha emitting isotopes. Due to the bombardment of Th-232 targets with 100 MeV protons, a high-energy n-γ mixed radiation field is generated. Here, we compared the calculated results for calculating the dose attenuation of neutrons in iron and concrete using FLUKA code and the analytical methods in standard DIN 6875-20. We analyzed the impact of carbon content on the shielding capabilities of iron, the results indicate that a small amount of carbon improves the shielding effect, and then compared the effects of different thicknesses of low-carbon steel and heavy concrete composite shielding on forward neutron dose attenuation. Additionally, we calculated and analyzed dose attenuation curves and energy spectra for 1 MeV and 20 MeV neutrons passing through heavy concrete, boron carbide, carbon steel, polyethylene, and borated polyethylene. The shielding capabilities of various materials and their combinations against the n-γ mixed field were compared, and then we optimized the lateral shielding compensation structures based on the results. Finally, we simulated the overall dose distribution of the target station. This study is particularly significant for engineering design of the target stations in the isotope production facilities.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 7","pages":"Article 103519"},"PeriodicalIF":2.6,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143681754","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Kinetic simulation of uranium migration in granite fissure media of beishan, gansu, China: A case study based on the Laplace transform and inverse transform methods","authors":"Xianzhe Duan ,&nbsp;Cong Du ,&nbsp;Nan Li ,&nbsp;Jiaxin Duan ,&nbsp;Zhenping Tang","doi":"10.1016/j.net.2024.09.008","DOIUrl":"10.1016/j.net.2024.09.008","url":null,"abstract":"<div><div>Deep geological disposal is currently considered the most practical and feasible method for disposing high-level radioactive wastes (HLWs). One of its key scientific issues is the migration of nuclides in fissure media. However, studies on the migration of nuclides like U-238 are relatively limited. In this study, the granite rock masses in Beishan, Gansu were selected to construct a physical and mathematical model of U-238 migration using the Laplace transform and inverse transform methods. Based on the numerical methods, the kinetic migration of nuclide U-238 in the fissure media of granite was simulated, and the effects of parameters such as fissure width, hydraulic gradient, diffusible area ratio and rock porosity on the migration of U-238 were investigated. The following insights were obtained: (1) After 100,000 years, U-238 has a very limited diffusion depth in the matrix domain, with a diffusion range of only a few tens of millimeters, whereas it migrates relatively quickly in the fissure domain, with a maximum migration distance of about 1500 m. (2) Under the same migration time and distance, the relative concentration of nuclide U-238 in the fissure domain increases with larger gap width, hydraulic gradient, and diffusible area ratio, but decreases with higher rock porosity. (3) In the same time range, the rock masses with larger gap widths, hydraulic gradients, and diffusible area ratios have larger migration ranges, while those with higher porosities have smaller migration ranges. (4) While selecting a site for diposal of HLWs, it is recommended to choose rock masses in the granite area of Beishan with no fissures or few fissures; additionally, areas with smaller fissure widths, hydraulic gradients, and diffusible area ratios but higher rock porosity should be prioritized. This study can provide important theoretical support for understanding nuclide migration in the future geological disposal of HLWs.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 2","pages":"Article 103205"},"PeriodicalIF":2.6,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142267046","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Criticality safety analysis for eccentric loading of fuel assemblies in spent nuclear fuel cask","authors":"Seok Geun Cho,&nbsp;Keon Il Cha,&nbsp;Kyoon Ho Cha","doi":"10.1016/j.net.2024.09.024","DOIUrl":"10.1016/j.net.2024.09.024","url":null,"abstract":"<div><div>Eccentric fuel loading is one of the studies performed in a spent nuclear fuel criticality safety analysis. Several studies have been performed to investigate the effect of increasing reactivity on eccentric loading and random displacement in spent nuclear fuel pools; However, studies within spent nuclear fuel casks have not been performed. Therefore, this study investigates the effects of eccentric loading and random displacement of fuel assemblies on the reactivity in the spent nuclear fuel cask. The spent nuclear fuel cask and PLUS7 fuel are modeled using the MCNP code to investigate these effects. The result indicates that in eccentric cases, the k-effective values exceed those observed in the normal case. Also, several random displacement cases show k-effective values that exceed the normal case. These results differ from previous studies on eccentric loading in the spent fuel pool. It supports the necessity of considering both eccentric loading and random displacement in the criticality safety analysis in spent nuclear fuel cask. The increase in reactivity due to eccentric loading and random displacement of fuel assemblies within casks might be considered in criticality safety analysis and regarded as an uncertainty.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 2","pages":"Article 103221"},"PeriodicalIF":2.6,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143099581","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Coupled heat and mass transfer simulation of CRUD migration and deposition in PWR systems","authors":"Xuesong Li,&nbsp;Meng Zhang,&nbsp;Yang Gao,&nbsp;Hongguo Hou,&nbsp;Caishan Jiao,&nbsp;Nan Chao","doi":"10.1016/j.net.2024.09.016","DOIUrl":"10.1016/j.net.2024.09.016","url":null,"abstract":"<div><div>In Pressurized Water Reactors (PWRs), corrosion products are released during operation due to the large contact area between the primary circuit coolant and the equipment materials. In this study, a multiphysics model was developed and validated to simulate and analyze the migration and deposition behavior of corrosion products in the primary circuit. The model is useful for calculating the effect of operating conditions on migration and deposition. The effects of mass transfer and subcooled boiling on deposition and re-release were included in the model. Diffusion, convective mass transfer, and transition between ions and particles in the coolant were also considered in the model.</div><div>The model's accuracy was validated by comparison with actual measured data from the Callaway reactor. Calculations showed that the deposition on the steam generator exceeded that on other equipment, primarily attributable to its larger surface area. Additionally, variations in the coolant flow significantly influence the deposition resulting from subcooled boiling, with an increase in flow leading to a noticeable reduction in boiling deposition.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 2","pages":"Article 103213"},"PeriodicalIF":2.6,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143099583","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Corrigendum to “Radiometric examination of fertilizers and assessment of their health hazards, commonly used in Pakistan” [Nucl. Eng. Tech. 55 (2023) 2447–2453]","authors":"Hannan Younis ,&nbsp;Sumbilah Shafique ,&nbsp;Zahida Ehsan ,&nbsp;Aleena Ishfaq ,&nbsp;Khurram Mehboob ,&nbsp;Muhammad Ajaz ,&nbsp;Abdullah Hidayat ,&nbsp;Wazir Muhammad","doi":"10.1016/j.net.2024.10.003","DOIUrl":"10.1016/j.net.2024.10.003","url":null,"abstract":"","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 2","pages":"Article 103241"},"PeriodicalIF":2.6,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143099596","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}