Nuclear Engineering and Technology最新文献_第7页

Enhancing equipment qualification testing facility for nuclear power plants: Achieving rapid temperature and pressure increase during design basis events 加强核电站的设备鉴定测试设施：在设计基础事件中实现温度和压力的快速上升

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-31 DOI: 10.1016/j.net.2024.07.058

Kyungha Ryu, Seonggyu Cho, Taeho Roh, Sangkyo Kim, Taekook Park, Taehyun Lee, Jongwon Park, Jaehyun Cho

引用次数: 0

Characterization of evolution of reactive transport parameters during leaching process of sandstone uranium ore by combining porosity and lacunarity 结合孔隙度和裂隙度分析砂岩型铀矿浸出过程中反应输运参数的演变特征

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-30 DOI: 10.1016/j.net.2024.07.057

Haiying Fu, Shuai Wang, Deming Tan, Guicheng He, Meng Lian, Zhonghua Zhu, Dexin Ding

{"title":"Characterization of evolution of reactive transport parameters during leaching process of sandstone uranium ore by combining porosity and lacunarity","authors":"Haiying Fu, Shuai Wang, Deming Tan, Guicheng He, Meng Lian, Zhonghua Zhu, Dexin Ding","doi":"10.1016/j.net.2024.07.057","DOIUrl":"https://doi.org/10.1016/j.net.2024.07.057","url":null,"abstract":"During the in-situ leaching process of sandstone uranium ore deposits, the dynamic evolution of reactive transport parameters, including permeability, tortuosity, and specific surface area (SSA), plays a crucial role in solution flow and solute transport. Characterizing the evolution of these parameters is essential for understanding the leaching process. However, the heterogeneous pore structure of sandstone renders porosity alone insufficient to capture changes in these parameters. This study combines porosity and lacunarity to comprehensively characterize these parameters. For this purpose, leaching experiments were conducted on sandstone uranium ore samples, and CT imaging was performed at different leaching time points. The evolution of reactive transport parameters was analyzed by studying cubic subsamples from the images. The results indicate that both porosity and lacunarity are significant factors influencing the reactive transport parameters. However, neither parameter alone adequately characterizes their evolution. In contrast, combining them accurately characterizes the evolution of reactive transport parameters. Porosity reflects pore quantity, while lacunarity represents pore heterogeneity. Combining these measures facilitates a comprehensive understanding of the evolution of reactive transport parameters and the influence of pore microstructure on macroscopic reactive transport parameters. This research provides valuable insights for optimizing the leaching process in sandstone uranium ore deposits.","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.7,"publicationDate":"2024-07-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141940111","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}

引用次数: 0

Social acceptance of small modular reactor (SMR): Evidence from a contingent valuation study in South Korea 小型模块化反应堆（SMR）的社会接受度：来自韩国或有估值研究的证据

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-30 DOI: 10.1016/j.net.2024.07.059

Eunjung Cho, Juyong Lee

{"title":"Social acceptance of small modular reactor (SMR): Evidence from a contingent valuation study in South Korea","authors":"Eunjung Cho, Juyong Lee","doi":"10.1016/j.net.2024.07.059","DOIUrl":"https://doi.org/10.1016/j.net.2024.07.059","url":null,"abstract":"This study provides a comprehensive analysis of the social acceptance of the Small Modular Reactor (SMR) in South Korea. The growing interest in SMRs as a potential solution to the challenges of climate change and energy security highlights the need for continued research and development in this area. The research was conducted using a contingent valuation method, which involved surveying a representative sample of the South Korean population. Out of a total of 1032 respondents, 78 % were willing to pay for SMR development. The mean WTP was estimated to be USD 4.28 per year per household and scaled up to the national level in South Korea, it was analysed to have a total economic and social benefit of USD 0.49 billion. The more serious the respondents perceived the current and future problem of climate change to be, the more likely they were to be willing to pay an offered bid amount. This study suggests that the need to address climate change and the need to raise awareness of SMR as one of the low-carbon technologies at the government level is required to generate the appropriate level of social acceptance to promote SMR development.","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.7,"publicationDate":"2024-07-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141940107","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}

引用次数: 0

The effect of zinc, iron and manganese content on gamma shielding properties of magnesium-based alloys produced using the powder metallurgy 锌、铁和锰含量对粉末冶金法生产的镁基合金伽马屏蔽性能的影响

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-25 DOI: 10.1016/j.net.2024.07.039

{"title":"The effect of zinc, iron and manganese content on gamma shielding properties of magnesium-based alloys produced using the powder metallurgy","authors":"","doi":"10.1016/j.net.2024.07.039","DOIUrl":"10.1016/j.net.2024.07.039","url":null,"abstract":"<div>This study investigates the effects of Zinc (Zn), Manganese (Mn), and Iron (Fe) additions on the microstructure, corrosion behaviour, biocompatibility, mechanical, and gamma-ray shielding properties of Magnesium (Mg) alloys prepared in various compositions using powder metallurgy (PM). The microstructure and mechanical properties of these alloys were analyzed using electron microscopes (SEM and FE-SEM) and X-ray diffraction (XRD) methods. The results showed positive changes in the material's structure when the percentage of zinc added to pure magnesium increased. It was observed that the material became ductile, and the ductile fracture increased when the zinc ratio increased. The gamma-ray shielding properties of newly produced Mg-based alloys have also been discussed since they have a high potential for use in space technologies. Radiation shielding measurements have been performed using a 3′′ × 3″ NaI(Tl) scintillation detector NaI (Tl) gamma-ray spectrometer. The gamma-ray shielding parameters such as the linear attenuation coefficients (μl), mass attenuation coefficient (μm), effective atomic number (Zeff), half-value layer (HVL), and tenth-value layer (TVL) have been determined experimentally at photon energies of 0.511 MeV (emitted from a22Na radioactive point source) and 1.173 MeV and 1.332 MeV (emitting from a60Co radioactive point source). The obtained parameters have been compared to the theoretical results of the XCOM software, and a satisfactory agreement has been found. It can be said from the results that the Mg30Zn alloy has the best shielding properties among the produced materials.</div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.6,"publicationDate":"2024-07-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S1738573324003553/pdfft?md5=128052f229f67b813b02811a9379a697&pid=1-s2.0-S1738573324003553-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141840766","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 ability to manage uncertainty for solid radioactive waste characterization in the UK nuclear industry 英国核工业固体放射性废物特征描述的不确定性管理能力

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-24 DOI: 10.1016/j.net.2024.07.050

Peter J. Hiller MSc BSc, Caroline K. Pyke MSc BSc, Chris P. Lennon BSc, Olivia C.G. Tuck MMathStat, Caitlin A. Painter BSc

引用次数: 0

The role of CO on initial oxidation behavior of α-U(001) surface: a first principles study CO 对 α-U(001) 表面初始氧化行为的作用：第一性原理研究

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-24 DOI: 10.1016/j.net.2024.07.051

Longxian Li, Min Zhu, Yan Li, Yanru Ren, Longfei Pu, Chengxuan Peng

引用次数: 0

Evaluation of particle-capturing ability of a hydrogel-based surface decontamination agent using simulated nuclear fallout particles 利用模拟核尘埃粒子评估水凝胶表面去污剂的粒子捕获能力

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-23 DOI: 10.1016/j.net.2024.07.047

Sung-Wook Kim, Hee-Man Yang, Hyung-Ju Kim

引用次数: 0

Defect Monitoring System of the Internal Structures of a Sodium Fast Reactor using an Artificial Intelligence Model 使用人工智能模型的钠快堆内部结构缺陷监测系统

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-23 DOI: 10.1016/j.net.2024.07.049

Hyungi Byun, Han Gil Lee, Beom Kyu Kim, Geun Dong Song, Bongsoo Lee

{"title":"Defect Monitoring System of the Internal Structures of a Sodium Fast Reactor using an Artificial Intelligence Model","authors":"Hyungi Byun, Han Gil Lee, Beom Kyu Kim, Geun Dong Song, Bongsoo Lee","doi":"10.1016/j.net.2024.07.049","DOIUrl":"https://doi.org/10.1016/j.net.2024.07.049","url":null,"abstract":"This study developed a defect-monitoring system with an artificial intelligence model, YOLOv7, which is tailored for processing image data from an ultrasonic visualization system within sodium fast reactor (SFR) internal structures. For the safety of SFR internal structures, although it is a crucial inspection for defect monitoring, it is difficult to identify structural defects because of the invisible environment. Therefore, we applied the YOLOv7 model in this study; however, we encountered challenges including decreased accuracy with complex defect shapes and complications from data augmentation during pre-training. To solve these problems, we additionally applied the enhanced super-resolution generative adversarial network for higher resolution and a Sobel noise-filtering algorithm to enhance the defect detection accuracy. And we evaluated our system by comparing it with a confidence score. This underscores the effectiveness of the approach in enhancing the defect detection capabilities. Therefore, this defect-monitoring system should be designed to preemptively identify internal structure deformations and enhance SFR safety and maintenance practices.","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.7,"publicationDate":"2024-07-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141771270","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}

引用次数: 0

CFD Simulation of Thermal Stratification and Mixing in a Nordic BWR Pressure Suppression Pool 北欧重水反应堆压力抑制池热分层和混合的 CFD 模拟

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-23 DOI: 10.1016/j.net.2024.07.045

Xicheng Wang, Govatsa Acharya, Dmitry Grishchenko, Pavel Kudinov

{"title":"CFD Simulation of Thermal Stratification and Mixing in a Nordic BWR Pressure Suppression Pool","authors":"Xicheng Wang, Govatsa Acharya, Dmitry Grishchenko, Pavel Kudinov","doi":"10.1016/j.net.2024.07.045","DOIUrl":"https://doi.org/10.1016/j.net.2024.07.045","url":null,"abstract":"Boiling Water Reactor (BWR) employs the Pressure Suppression Pool (PSP) as a heat sink to prevent overpressure of the reactor vessel and containment. Steam can be injected into the PSP through spargers in normal and accident conditions and through blowdown pipes in case of a loss of coolant accident (LOCA). There is a safety limit on the maximum PSP temperature at which such steam injection might cause dynamic loads on the containment structures. The performance of the pool can be affected if thermal stratification is developed when temperature of the hot layer grows rapidly while cold layer remains inactive. Simulation of pool behavior during realistic accident scenarios requires validated models that can sufficiently address the interaction between phenomena, safety systems and operational procedures. Direct modeling of steam injection into a water pool in long-term transients is computationally expensive due to the need to resolve simultaneously the smallest space and time scales of individual steam bubbles and the scales of the whole PSP. To enable PSP analysis for practical purposes, Effective Heat source and Effective Momentum source (EHS/EMS) models have been proposed that avoid the need to resolve steam-water interface. This paper aims to implement mechanistic approaches previously developed by authors for the simulation of transient thermal stratification and mixing phenomena induced by steam injection through spargers in a Nordic BWR PSP. The latest version of the EHS/EMS models using the ‘Unit cell’ approach has been validated against integral effect pool tests and applied to plant simulations. Several scenarios with boundary conditions corresponding to postulated accident sequences were simulated to investigate the possibility of stratification development and the effects of activation of different systems (e.g., blowdown pipes, high momentum nozzle) on the pool behavior.","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.7,"publicationDate":"2024-07-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141771274","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}

引用次数: 0

ASSESSMENT OF LOOK-UP TABLES FOR THE PREDICTION OF HEAT TRANSFER COEFFICIENT DISTRIBUTION IN ROD BUNDLES COOLED BY SUPERCRITICAL WATER 评估用于预测超临界水冷却棒束传热系数分布的查找表

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-22 DOI: 10.1016/j.net.2024.07.044

Rashed MD. Sardar, Akhmed M. Baisov

引用次数: 0