Nuclear Engineering and Technology最新文献_第7页

Influence of dissolved hydrogen and IG Cr carbide on the oxidation behavior of Alloy 600 in hydrogenated primary water 溶解氢和 IG 碳化铬对合金 600 在氢化原水中氧化行为的影响

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-08-03 DOI: 10.1016/j.net.2024.08.003

Yun Soo Lim, Dong Jin Kim, Sung Woo Kim, Seong Sik Hwang, Sung Hwan Cho, Hong Pyo Kim

{"title":"Influence of dissolved hydrogen and IG Cr carbide on the oxidation behavior of Alloy 600 in hydrogenated primary water","authors":"Yun Soo Lim, Dong Jin Kim, Sung Woo Kim, Seong Sik Hwang, Sung Hwan Cho, Hong Pyo Kim","doi":"10.1016/j.net.2024.08.003","DOIUrl":"https://doi.org/10.1016/j.net.2024.08.003","url":null,"abstract":"The internal oxidation (IO) and preferential intergranular oxidation (PIO) behavior of Alloy 600 depending on the dissolved hydrogen (DH) content and the IG Cr carbide in hydrogenated primary water were characterized in detail using analytical electron microscopy techniques. The oxidation layer was unstable when the DH concentration was such that Ni was in the vicinity of Ni/NiO equilibrium and it could easily be peeled off. Hence, the grain boundaries of the bare metal were attacked. PIO occurred and Cr-rich oxide identified as CrO was formed at the oxidized grain boundary. NiO emerged when the DH concentration was such that Ni was in an oxidizing state, whereas Ni enrichment occurred inside the oxidized grain boundary when the DH concentration was such that Ni was in a reducing state with respective to Ni/NiO equilibrium. The IG Cr carbide strongly affected the PIO behavior by means of the consumption of oxygen penetrating into the grain boundary. The depth of the IO layer decreased as the DH concentration increased. The different oxidation behaviors depending on the DH content and IG Cr carbide are believed to affect the PWSCC resistance of Alloy 600 significantly.","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"6 1","pages":""},"PeriodicalIF":2.7,"publicationDate":"2024-08-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141940106","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

Technical studies about the prestressed insulation cylinder of HL-3 tokamak's center-post 有关 HL-3 托卡马克中柱预应力绝缘筒的技术研究

IF 2.7 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-08-03 DOI: 10.1016/j.net.2024.08.001

Yin Qiu, Ming Li, Xiaolong Liu, Qinghua Ren, Tao Lin, Jian Liu

引用次数: 0

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":"53 1","pages":""},"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":"78 1","pages":""},"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":"95 1","pages":""},"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><p>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 (<em>μ</em><sub><em>l</em></sub>), mass attenuation coefficient (<em>μ</em><sub><em>m</em></sub>), effective atomic number (<em>Z</em><sub><em>eff</em></sub>), half-value layer (HVL), and tenth-value layer (TVL) have been determined experimentally at photon energies of 0.511 MeV (emitted from a<sup>22</sup>Na radioactive point source) and 1.173 MeV and 1.332 MeV (emitting from a<sup>60</sup>Co 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.</p></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"56 9","pages":"Pages 3872-3883"},"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

Leveraging physics-informed neural computing for transport simulations of nuclear fusion plasmas 利用物理信息神经计算进行核聚变等离子体的传输模拟

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-25 DOI: 10.1016/j.net.2024.07.048

J. Seo, I.H. Kim, H. Nam

{"title":"Leveraging physics-informed neural computing for transport simulations of nuclear fusion plasmas","authors":"J. Seo, I.H. Kim, H. Nam","doi":"10.1016/j.net.2024.07.048","DOIUrl":"10.1016/j.net.2024.07.048","url":null,"abstract":"<div><div>For decades, plasma transport simulations in tokamaks have used the finite difference method (FDM), a relatively simple scheme to solve the transport equations, a coupled set of time-dependent partial differential equations. In this FDM approach, typically over <span><math><mrow><mi>O</mi><mrow><mo>(</mo><mn>1</mn><msup><mrow><mn>0</mn></mrow><mrow><mn>5</mn></mrow></msup><mo>)</mo></mrow></mrow></math></span> time steps are needed for a single discharge, to mitigate numerical instabilities induced by stiff transport coefficients. It requires significant computing time as costly transport models are repeatedly called in a serial manner, proportional to the number of time steps. Additionally, the unidirectional calculations of FDM make it difficult to predict regions prior to the initial condition or apply additional temporal constraints. In this study, we discuss using a new scheme to solve plasma transport based on physics-informed neural networks (PINNs). PINN iteratively updates a function that maps spatiotemporal coordinates to plasma states, gradually reducing errors in transport equations. The required number of updates in PINNs is several orders of magnitude less than the chronological iterations in FDM. Furthermore, it is free from numerical instabilities arising from finite grids and enables more versatile semi-predictive simulations with arbitrary spatiotemporal constraints. In this paper, we discuss the features and potentials of the tokamak transport solver using PINNs through comparisons with FDM, and also its drawbacks and challenges.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"56 12","pages":"Pages 5396-5404"},"PeriodicalIF":2.6,"publicationDate":"2024-07-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141839514","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

Uranium quantification in radioactive waste drums using In-Situ Object Counting System (ISOCS) for safeguards purposes 利用原位物体计数系统（ISOCS）对放射性废物桶中的铀进行定量，以达到保障目的

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2024-07-25 DOI: 10.1016/j.net.2024.07.040

Jihyun Ahn , Seungmin Lee , Hee Seo

{"title":"Uranium quantification in radioactive waste drums using In-Situ Object Counting System (ISOCS) for safeguards purposes","authors":"Jihyun Ahn , Seungmin Lee , Hee Seo","doi":"10.1016/j.net.2024.07.040","DOIUrl":"10.1016/j.net.2024.07.040","url":null,"abstract":"<div><div>For the peaceful use of nuclear energy, materials, and technology, various methods have been developed for safeguards purposes. Among them, the In-Situ Object Counting System has demonstrated its usefulness and reliability in various nuclear material verification activities, due to its capability of operating without standard materials. In the present study, the performance of In-Situ Object Counting System for uranium quantification was evaluated using an experimental drum at KEPCO NF as well as low-level radioactive waste drums at the Korea Radioactive Waste Agency. The results showed that In-Situ Object Counting System could quantify uranium in radioactive waste drums, with a relative error ranging from −1 to −67 % compared with destructive assay results. This study also examined, using the Monte Carlo N-particle transport 6.2 code, the factors that affect uncertainty in uranium quantification: geometrical conditions, spectrum quality, heterogeneity, and the self-shielding effect. These findings could prove useful in efforts to optimize the In-Situ Object Counting System as a tool for nuclear material verification in the safeguards context.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"56 12","pages":"Pages 5313-5319"},"PeriodicalIF":2.6,"publicationDate":"2024-07-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141840311","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