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Dynamic behavior of duplex stainless steel with improved chloride-induced stress corrosion cracking resistance in drop scenarios for dry storage containers
IF 2.6 3区 工程技术
Nuclear Engineering and Technology Pub Date : 2025-02-06 DOI: 10.1016/j.net.2025.103522
Hyungyu Roh , Ki-Wan Seo , Chaewon Jeong , Ji-Hye Kim , No-Cheol Park , Yun-Jae Kim , Changheui Jang
{"title":"Dynamic behavior of duplex stainless steel with improved chloride-induced stress corrosion cracking resistance in drop scenarios for dry storage containers","authors":"Hyungyu Roh ,&nbsp;Ki-Wan Seo ,&nbsp;Chaewon Jeong ,&nbsp;Ji-Hye Kim ,&nbsp;No-Cheol Park ,&nbsp;Yun-Jae Kim ,&nbsp;Changheui Jang","doi":"10.1016/j.net.2025.103522","DOIUrl":"10.1016/j.net.2025.103522","url":null,"abstract":"<div><div>This study investigated the safety and structural integrity enhancements in dry storage containers (DSCs) achieved using a novel duplex stainless steel with a composition of Fe-19Cr-4Ni-2.5Mo-4.5Mn, referred to as advanced duplex stainless steel for a canister of dry storage (ADCS). This material was developed to improve resistance to chloride-induced stress corrosion cracking. The safety and structural integrity of DSCs utilizing ADCS and conventional austenitic stainless steel (ASS) were comparatively evaluated using finite element analysis based on detailed DSC models for vertical, oblique, and horizontal drops under accident scenarios, in accordance with International Atomic Energy Agency and U.S. Nuclear Regulatory Commission regulations. The results confirmed that ADCS significantly improved impact resistance and reduced plastic strain under impact conditions. Consequently, DSCs incorporating ADCS offer higher safety and reliability during both transportation and storage than those using conventional ASS. Furthermore, by leveraging these advantages of ADCS, DSCs can be made lighter while maintaining safety and structural integrity. Additionally, strain-based evaluations, consistent with ASME BPVC Sec. III Div. 3, demonstrated that higher margins could be achieved using ADCS where plastic deformation occurred. This highlights that ADCS is a promising material for ensuring greater structural integrity and safety in DSCs.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 7","pages":"Article 103522"},"PeriodicalIF":2.6,"publicationDate":"2025-02-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143681668","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}
引用次数: 0
Dosimetric and energy deposition evaluation of the dual-microcavity capsule structure for glioma 125I brachytherapy using Monte Carlo simulation
IF 2.6 3区 工程技术
Nuclear Engineering and Technology Pub Date : 2025-02-06 DOI: 10.1016/j.net.2025.103484
Dongjie Li , Yu Liang , Gang Yao , Zhongbao Guan , Weida Gao
{"title":"Dosimetric and energy deposition evaluation of the dual-microcavity capsule structure for glioma 125I brachytherapy using Monte Carlo simulation","authors":"Dongjie Li ,&nbsp;Yu Liang ,&nbsp;Gang Yao ,&nbsp;Zhongbao Guan ,&nbsp;Weida Gao","doi":"10.1016/j.net.2025.103484","DOIUrl":"10.1016/j.net.2025.103484","url":null,"abstract":"<div><div>Brachytherapy has emerged as a primary approach for tumor treatment, and determining the dosimetric parameters of the radiation source is a critical step in radiation therapy, as recommended by the American Association of Physicists in Medicine (AAPM). This study investigates a novel dual-cavity capsule for combined radiotherapy and chemotherapy treatment. Monte Carlo simulations were used to obtain the dosimetric parameters and energy deposition distribution of the dual-cavity structure within a water phantom. The simulation results were then compared with published data for other commercial <sup>125</sup>I seeds. The results show that the dose-rate constant for the dual-cavity capsule is (0.984 ± 0.020) cGy·h<sup>−1</sup>U<sup>−1</sup>, which aligns with values reported for other commercial <sup>125</sup>I seeds. The radial dose function and anisotropy function of the dual-cavity capsule generally match reference data for these seeds, though notable differences were observed at specific positions. When the source activity was set to 1 mCi, the dose rate at the center of the dual-cavity capsule was 12.40 cGy/h, compared to 13.07 cGy/h for a single-cavity structure containing only a radiotherapy channel, showing a dose rate difference of approximately 5 %. The presence of the chemotherapy channel caused a shift in the peak dose rate within the dual-cavity structure but had minimal effect on the overall radiotherapy dose distribution. The dual-cavity capsule demonstrates a high central dose rate, with a rapid dose fall-off toward the periphery. Due to structural and material modifications, the radial dose function and anisotropy function of the dual-cavity capsule deviate from the assumptions of the AAPM TG-43U1 formalism, indicating that the TG-43U1 two-dimensional dose-rate equations may not fully apply to this novel design. This study serves as a valuable reference for establishing spatial dosimetric parameters for the dual-cavity capsule structure in clinical practice.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 7","pages":"Article 103484"},"PeriodicalIF":2.6,"publicationDate":"2025-02-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143682106","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}
引用次数: 0
In-situ estimation of gamma-ray source location at a specific depth based on a coded-aperture gamma camera
IF 2.6 3区 工程技术
Nuclear Engineering and Technology Pub Date : 2025-02-06 DOI: 10.1016/j.net.2025.103483
Dukwoo Kim, Manhee Jeong
{"title":"In-situ estimation of gamma-ray source location at a specific depth based on a coded-aperture gamma camera","authors":"Dukwoo Kim,&nbsp;Manhee Jeong","doi":"10.1016/j.net.2025.103483","DOIUrl":"10.1016/j.net.2025.103483","url":null,"abstract":"<div><div>The coded-aperture gamma imager, EPSILON-G, was employed to swiftly identify gamma-ray sources in-situ. EPSILON-G is a device that gathers data using a detector module that integrates a GAGG(Ce) scintillator with a SiPM array and accurately locates gamma-ray sources through image reconstruction. To confirm its imaging capability and performance in-situ, the minimum count rate for imaging (MCI) was determined using MCNPX-PoliMi code simulations. Using the MCI, the minimum detectable activity (MDA) was calculated as representing the concentration at which surface radioactivity can be feasibly reconstructed in-situ. Additionally, a depth estimation method utilizing dual image acquisition was developed to identify radioactive materials at specific surface depths during radiological emergencies. This depth estimation method was theoretically proposed and validated through experiments with a<sup>137</sup>Cs gamma-ray source. The MDA satisfying the MCI for soil standards was 3.663 Bq/g. In-situ depth estimation experiments using a sandbox enabled the depth to be estimated up to 24.9 ± 2.3 cm with the <sup>137</sup>Cs (3.5 MBq) source.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 7","pages":"Article 103483"},"PeriodicalIF":2.6,"publicationDate":"2025-02-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143682183","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}
引用次数: 0
Development of real-time path-based 3D dose rate mapping system
IF 2.6 3区 工程技术
Nuclear Engineering and Technology Pub Date : 2025-02-05 DOI: 10.1016/j.net.2025.103464
Dahui Kwack , Pyeongwon Park , Yongkwon Kim , Bohyun Ryu
{"title":"Development of real-time path-based 3D dose rate mapping system","authors":"Dahui Kwack ,&nbsp;Pyeongwon Park ,&nbsp;Yongkwon Kim ,&nbsp;Bohyun Ryu","doi":"10.1016/j.net.2025.103464","DOIUrl":"10.1016/j.net.2025.103464","url":null,"abstract":"<div><div>According to the ALARA principle, workers in radiation field must use dosimeters at working sites to ensure that annual effective dose does not exceed 50 mSv. However, traditional dosimeters assess radiation levels only after post-processing, which lack a real-time monitoring system. To overcome this limitation, a real-time path-based 3D exposure dose mapping system was developed by integrating a survey-meter and a 3D scanner using the SLAM (Simultaneous Localization and Mapping) algorithm. This advanced system allows simultaneous spatial scanning and dose measurement, enabling free movement in complex indoor/outdoor environments. As workers navigate the area, the system generates a point cloud dataset (PCD) of the environment, recording that coordinates and measured dose rates. This dataset is visually presented in real-time, following the worker's path in 3D space. Additionally, a Deep Neural Network (DNN) model was created to produce a 3D dose rate distribution map. By using the path coordinates as input and corresponding doses as output, the model predicts dose rate throughout the entire PCD. These predictions were used to create a 3D map, with color and brightness adjusted based on dose rates. The system was implemented with LiDAR and a Geiger-Müller detector, then successfully tested in preliminary experiments.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 6","pages":"Article 103464"},"PeriodicalIF":2.6,"publicationDate":"2025-02-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143679329","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}
引用次数: 0
Dual on-premises storage framework for memory optimization and secure data transmission in nuclear power plants
IF 2.6 3区 工程技术
Nuclear Engineering and Technology Pub Date : 2025-02-05 DOI: 10.1016/j.net.2025.103526
Niayesh Gharaei
{"title":"Dual on-premises storage framework for memory optimization and secure data transmission in nuclear power plants","authors":"Niayesh Gharaei","doi":"10.1016/j.net.2025.103526","DOIUrl":"10.1016/j.net.2025.103526","url":null,"abstract":"<div><div>In nuclear power plants, efficiently managing sensitive data and ensuring secure transmission between nodes and storage systems are critical for maintaining operational integrity and safety. This paper proposes a novel approach utilizing dual on-premises storages to enhance memory efficiency and ensure secure data transmission. By segregating sensitive and non-sensitive data into distinct storage units, the system optimizes memory utilization while maintaining robust security protocols for data transfer between Base Stations (BS) and storage nodes. The architecture integrates advanced encryption techniques and secure protocols to safeguard data integrity during transmission, thereby mitigating risks associated with unauthorized access and data breaches. Experimental validation and performance analysis an average improvement of 25 % across encryption time, decryption time, failure rate, and latency metrics compared to existing methods.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 7","pages":"Article 103526"},"PeriodicalIF":2.6,"publicationDate":"2025-02-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143681746","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}
引用次数: 0
Assessing radiological properties of novel tissue equivalent materials for heterogeneous pediatric head phantom: Experimental insights and Monte Carlo simulations
IF 2.6 3区 工程技术
Nuclear Engineering and Technology Pub Date : 2025-02-04 DOI: 10.1016/j.net.2025.103525
Hamza Sekkat , Abdellah Khallouqi , Omar El rhazouani , Youssef Madkouri , Abdellah Halimi
{"title":"Assessing radiological properties of novel tissue equivalent materials for heterogeneous pediatric head phantom: Experimental insights and Monte Carlo simulations","authors":"Hamza Sekkat ,&nbsp;Abdellah Khallouqi ,&nbsp;Omar El rhazouani ,&nbsp;Youssef Madkouri ,&nbsp;Abdellah Halimi","doi":"10.1016/j.net.2025.103525","DOIUrl":"10.1016/j.net.2025.103525","url":null,"abstract":"<div><div>This study addresses the need for realistic substitute materials in pediatric head CT to enhance imaging safety. Epoxy resin-based composites were developed to mimic cranial bone, brain tissue, cerebrospinal fluid and eye lens. Radiological properties were validated using Monte Carlo simulations and XMuDat software, with CT numbers measured on a 64-detector CT scanner at 80, 100, and 120 kVp. A comparison was applied against standard tissues from the International Commission on Radiation Units and Measurements (ICRU). For cranial bone, a composite of 70 % epoxy resin and 30 % calcium carbonate achieved a density of 1.65 g/cm³ and Z<sub>eff</sub> = 11.02, with deviations in mass attenuation coefficients from ICRU standard ranging from 17.4 % at 40 keV to 1.2 % at 150 keV. Brain matter (95 % resin, 5 % acetone) achieved Z<sub>eff</sub> = 6.19, with deviations from the ICRU standard ranging from 13.7 % to 5.5 %. CSF (80 % resin, 15 % silica, 5 % acetone) closely matched water, with deviations from the water standard ranging from 3.4 % to 1.1 %. Eye lens (95 % resin, 5 % sodium bicarbonate) achieved Z<sub>eff</sub> = 6.47, with deviations from ICRU standard ranging from 7.5 % to 4.2 %. These results demonstrate the potential of epoxy resin-based substitutes to approximate ICRU standard tissues supporting safer pediatric radiology protocols customized to this sensitive population.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 7","pages":"Article 103525"},"PeriodicalIF":2.6,"publicationDate":"2025-02-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143681845","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}
引用次数: 0
Synthetic data for radioactive waste management: A comparative study for disused sealed radioactive sources in Indonesia
IF 2.6 3区 工程技术
Nuclear Engineering and Technology Pub Date : 2025-02-04 DOI: 10.1016/j.net.2025.103524
Pendi Rusadi , Zico Pratama Putra , Ajrieh Setyawan , Moch Romli , Muhammad Yusuf , Hendra Adhi Pratama , Raden Sumarbagiono
{"title":"Synthetic data for radioactive waste management: A comparative study for disused sealed radioactive sources in Indonesia","authors":"Pendi Rusadi ,&nbsp;Zico Pratama Putra ,&nbsp;Ajrieh Setyawan ,&nbsp;Moch Romli ,&nbsp;Muhammad Yusuf ,&nbsp;Hendra Adhi Pratama ,&nbsp;Raden Sumarbagiono","doi":"10.1016/j.net.2025.103524","DOIUrl":"10.1016/j.net.2025.103524","url":null,"abstract":"<div><div>This study addresses the need to generate reliable synthetic data in radioactive waste management, specifically on DSRSwhich will be integrated into a machine learning-based data management system focusing on Indonesia's Radioactive Waste Treatment Installation. Five distinct synthetic data generation methods such as Monte Carlo Gaussian, Data Augmentation, Copula Models, Bayesian Network, and VAEsrs are evaluated for their efficacy in replicating the statistical characteristics of confidential DSRS data. The evaluation criteria include the methods' ability to emulate the original data distribution, handle outliers, and their implications for DSRS management in predictive modelling. Bayesian Networks closely match the original dataset (with MRE = 17.60 %, Kolmogorov-Smirnov D<sub>n</sub> = 0.03, <em>p-value</em> = 0.31), making them the most effective method for generating synthetic data with high mean consistency. The results show Bayesian Network methods is the most suitable and effective methods for generating synthetic data that closely aligns with the original dataset in terms of mean consistency. These findings demonstrate that synthetic data can improve DSRS management, guiding future research and regulatory compliance.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 7","pages":"Article 103524"},"PeriodicalIF":2.6,"publicationDate":"2025-02-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143681672","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}
引用次数: 0
An improved two-temperature method for computing the temperature distributions within a TRISO-coated particle pebble fuel
IF 2.6 3区 工程技术
Nuclear Engineering and Technology Pub Date : 2025-02-04 DOI: 10.1016/j.net.2025.103515
Dali Yu , Fangnian Wang , Huaping Mei , Xiongwei Cheng , Chengjun Duan
{"title":"An improved two-temperature method for computing the temperature distributions within a TRISO-coated particle pebble fuel","authors":"Dali Yu ,&nbsp;Fangnian Wang ,&nbsp;Huaping Mei ,&nbsp;Xiongwei Cheng ,&nbsp;Chengjun Duan","doi":"10.1016/j.net.2025.103515","DOIUrl":"10.1016/j.net.2025.103515","url":null,"abstract":"<div><div>With the world’s first pebble-bed modular high-temperature gas-cooled reactor beginning commercial operation in China, the tristructural-isotropic (TRISO) coated particle pebble fuel technology has garnered significant research interest and widespread attention. In light of the fact that temperature gradients within a pebble fuel may span several hundred degrees Celsius, it becomes imperative to attain a more precise and rapid determination of the internal temperature distribution. This work first developed an Improved Two-temperature Method (ITM) based on the analogous nature of heat and neutron diffusion processes, with deriving equations for three parameters <span><math><msub><mrow><mi>k</mi></mrow><mrow><mi>f</mi></mrow></msub></math></span>, <span><math><msub><mrow><mi>k</mi></mrow><mrow><mi>m</mi></mrow></msub></math></span>, and <span><math><mi>μ</mi></math></span>, to achieve higher accuracy and wider application range. Then, seven tests were implemented for validating the ITM through comparing with finite element method, which can be considered identical with the analytic solution. Results show that the ITM can provide very accurate predictions of the peak temperature of both the fuel particles and the matrix. Finally, analysis of the influences of packing fraction and particle diameter on the temperature distribution within a pebble fuel, has been investigated, and it was found that there are two competing mechanisms resulting in the optimized design occurs at the packing fraction of 0.05, and the smallest particle diameter of 0.2 mm. The developed ITM and findings in this work provide tools and thermal conditions for analyzing fission gas release, creep rate, and other performance metrics of the pebble fuel.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 7","pages":"Article 103515"},"PeriodicalIF":2.6,"publicationDate":"2025-02-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143681761","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}
引用次数: 0
The consequences of proton irradiation of KLuP2O7 doped with Pr3+ ions
IF 2.6 3区 工程技术
Nuclear Engineering and Technology Pub Date : 2025-02-04 DOI: 10.1016/j.net.2025.103523
S.A. Kiselev , V.A. Pustovarov , M.N. Sarychev , M.O. Kalinkin
{"title":"The consequences of proton irradiation of KLuP2O7 doped with Pr3+ ions","authors":"S.A. Kiselev ,&nbsp;V.A. Pustovarov ,&nbsp;M.N. Sarychev ,&nbsp;M.O. Kalinkin","doi":"10.1016/j.net.2025.103523","DOIUrl":"10.1016/j.net.2025.103523","url":null,"abstract":"<div><div>In this report spectroscopic properties of KLuP<sub>2</sub>O<sub>7</sub> phosphate doped with Pr<sup>3+</sup> ions are presented. Among the presented results, there are spectra of photoluminescence (PL) at room temperature and T = 5 K, excited with selective UV photons, spectra of PL excitation, and electron spin resonance (ESR) measurements. Measurements of luminescence spectra were performed with non-irradiated samples and after irradiation with protons (E = 18 MeV). Measurements of ESR spectra were carried out after irradiation with fast electrons (E = 10 MeV). In the studied samples doped with Pr<sup>3+</sup> ions, three typical channels of radiative relaxation of electron excitations were observed: interconfigurational <em>d</em><strong>→</strong><em>f</em> transitions, intraconfigurational <em>f</em><strong>→</strong><em>f</em> transitions and defect-related luminescence. After irradiation significant changes in emission characteristics were observed, including a redistribution of the intensity of interconfigurational transitions, an increase in defect-related luminescence and the manifestation of new emission centers. The generation of radiation-induced defects presumably occurs through the formation of complexes composed of phosphorus and oxygen atoms.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 7","pages":"Article 103523"},"PeriodicalIF":2.6,"publicationDate":"2025-02-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143681844","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}
引用次数: 0
Experimental research on fluid elastic instability in rod bundles subjected to lead-bismuth eutectic (LBE) cross-flow
IF 2.6 3区 工程技术
Nuclear Engineering and Technology Pub Date : 2025-02-03 DOI: 10.1016/j.net.2025.103514
Yibo Yin, Puzhen Gao, Xinyang Yu, Junshuai Sun, Jiming Wen, Ruifeng Tian
{"title":"Experimental research on fluid elastic instability in rod bundles subjected to lead-bismuth eutectic (LBE) cross-flow","authors":"Yibo Yin,&nbsp;Puzhen Gao,&nbsp;Xinyang Yu,&nbsp;Junshuai Sun,&nbsp;Jiming Wen,&nbsp;Ruifeng Tian","doi":"10.1016/j.net.2025.103514","DOIUrl":"10.1016/j.net.2025.103514","url":null,"abstract":"<div><div>Flow-induced vibration (FIV) is a common cause of equipment breakdown and is prevalent in engineering applications. Lead-bismuth eutectic (LBE) fluid has emerged as a new heat exchange medium in recent years. Understanding the FIV characteristics of rod bundles in liquid LBE is crucial for engineering issues such as the design of rod bundle arrangements and the safety validation of heat exchangers. Based on a designed FIV experimental system in LBE, this paper primarily investigates the fluid elastic instability (FEI) characteristics of rod bundles in cross-flow LBE. The vibration time-history curve and spectral responses at various reduced velocities were analyzed. The effect of surrounding rod stiffness, arrangement pattern, and pitch ratio on the critical reduced velocity (<em>V</em><sub>pcr</sub>) under different rod bundle configurations was investigated. The results show that in LBE, within the pitch ratio range of 1.6–2.5, for cantilever beam-type rod bundles, the effect of vortex shedding on the rod bundle cannot be ignored in LBE. Strouhal number (<em>St</em>) for the normal triangle rod bundles composed of fully flexible rods and non-fully flexible rods with a pitch ratio of 1.6 in LBE is 0.203 and 0.315, respectively. Streamwise FEI is strongly correlated with inter-rod coupling, and arranging flexible rods around the rod can induce streamwise FEI. Although inter-rod coupling is not the main factor affecting transverse FEI, as the number of flexible rods increases, the <em>V</em><sub>pcr</sub> for transverse FEI decreases. Arranging flexible rods around the rod reduces the stability of the rod bundle. Within the pitch ratio range of 1.6–2.5, as the pitch ratio increases, the <em>V</em><sub>pcr</sub> decreases, and the permissible inlet velocity increases. When the pitch ratio is 1.6, the <em>V</em><sub>pcr</sub> for streamwise FEI is nearly the same as that for transverse FEI, with streamwise FEI more likely to occur in the central rod. When the pitch ratio is 2.5, transverses FEI occurs earlier than streamwise FEI, and the <em>V</em><sub>pcr</sub> for the central rod and downstream rod are almost the same. When the pitch ratio is 1.6, the downstream rod is located at the end of the rod bundle, which is not synchronized with the vibration of the central rod. When the pitch-to-diameter ratio is 2.5, the central rod and downstream rod vibrate in nearly perfect synchronization.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 7","pages":"Article 103514"},"PeriodicalIF":2.6,"publicationDate":"2025-02-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143681760","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}
引用次数: 0
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