Nuclear Engineering and Technology最新文献_第7页

Rapid determination of the migration parameters of nuclides in intact granite rock under the action of electric field 在电场作用下快速测定完整花岗岩石中核素的迁移参数

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-08-02 DOI: 10.1016/j.net.2024.07.062

Xinyu Wang, Xiaojie Li, Yongmei Li, Longcheng Liu, Shuo Meng, Chunguang Li, Zhenzhong Liu, Xiaodong Li, Kaixuan Tan

{"title":"Rapid determination of the migration parameters of nuclides in intact granite rock under the action of electric field","authors":"Xinyu Wang, Xiaojie Li, Yongmei Li, Longcheng Liu, Shuo Meng, Chunguang Li, Zhenzhong Liu, Xiaodong Li, Kaixuan Tan","doi":"10.1016/j.net.2024.07.062","DOIUrl":"https://doi.org/10.1016/j.net.2024.07.062","url":null,"abstract":"Deep geologic disposal has been widely accepted as a strategy for long-term disposal of the high-level radioactive waste. It is principal to obtain the migration parameters of radionuclides in natural barrier, such as granite, of a high-level radioactive waste repository for safety assessment of the repository. To quickly determine the diffusion and sorption properties of nuclides in intact granite, two tracers, I and ReO, were tested with a modified electromigration device, by imposing a constant voltage over an intact Beishan granitic rock sample. The breakthrough curves of I and ReO were obtained under condition of five different voltages. To interpret the electromigration experimental results with more confidence, an advection-dispersion model based on first-order adsorption kinetics was developed in this study. Data analysis of the breakthrough curves by this model suggest that the effective diffusion coefficients of I and ReO in intact Beishan granodiorite rock are (6.81 ± 0.53) × 10 m/s and (6.45 ± 0.07) × 10 m/s, respectively. While the distribution coefficient of the two ions are (9.06 ± 1.13) × 10 m/kg and (9.81 ± 0.13) × 10 m/kg, respectively. This indicates that I and ReO hardly adsorb in Beishan granodiorite rock.","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.7,"publicationDate":"2024-08-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141940108","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

Investigation on structural failure criteria and material property uncertainties of prestressed concrete containment structure 预应力混凝土安全壳结构失效标准和材料特性不确定性研究

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-08-02 DOI: 10.1016/j.net.2024.07.060

Woo-Min Cho, Han-Sang Woo, Yoon-Suk Chang

引用次数: 0

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

Mesut Ramazan Ekici , Emre Tabar , Gamze Hoşgör , Emrah Bulut , Ahmet Atasoy

{"title":"The effect of zinc, iron and manganese content on gamma shielding properties of magnesium-based alloys produced using the powder metallurgy","authors":"Mesut Ramazan Ekici , Emre Tabar , Gamze Hoşgör , Emrah Bulut , Ahmet Atasoy","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