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Analysis of the Long-Term Interaction Between Molten Core and Dry Concrete at Fukushima Daiichi Unit 1 福岛第一核电站 1 号机组熔融岩心与干混凝土之间的长期相互作用分析
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-24 DOI: 10.1080/00295450.2024.2371267
Marco Pellegrini, Christophe Journeau, Nathalie Seiler, Luis E. Herranz, M. García, Claus Spengler, Charlaine Bouillet, Marc Barrachin, David Luxat, Lucas Albright
{"title":"Analysis of the Long-Term Interaction Between Molten Core and Dry Concrete at Fukushima Daiichi Unit 1","authors":"Marco Pellegrini, Christophe Journeau, Nathalie Seiler, Luis E. Herranz, M. García, Claus Spengler, Charlaine Bouillet, Marc Barrachin, David Luxat, Lucas Albright","doi":"10.1080/00295450.2024.2371267","DOIUrl":"https://doi.org/10.1080/00295450.2024.2371267","url":null,"abstract":"The latest investigations of Fukushima Daiichi Unit 1 have demonstrated that corium attack to the pedestal walls and pedestal floor has occurred in Fukushima Daiichi Unit 1 to a certain extent. The...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"97 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-07-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141886191","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Exploring the Feasibility of Quantum-Based Secure Communications for Nuclear Applications 探索核应用中基于量子的安全通信的可行性
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-19 DOI: 10.1080/00295450.2024.2368977
Konstantinos Gkouliaras, Vasileios Theos, Stylianos Chatzidakis
{"title":"Exploring the Feasibility of Quantum-Based Secure Communications for Nuclear Applications","authors":"Konstantinos Gkouliaras, Vasileios Theos, Stylianos Chatzidakis","doi":"10.1080/00295450.2024.2368977","DOIUrl":"https://doi.org/10.1080/00295450.2024.2368977","url":null,"abstract":"Recent advancements in reactor designs could offer new revolutionary capabilities, including remote monitoring, increased flexibility, and reduced operation and maintenance costs. Embracing new dig...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"35 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-07-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141744763","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Research on Active Disturbance Rejection Control of Small Modular Reactor Once-Through Steam Generator Based on Differential Evolution Optimization Algorithm 基于差分进化优化算法的小型模块化反应堆一次蒸汽发生器主动干扰抑制控制研究
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-18 DOI: 10.1080/00295450.2024.2368973
Wei Guo, Bo Shi, Tao Zhang, Zhijiang Wu, Guohua Xiong, Minjun Peng
{"title":"Research on Active Disturbance Rejection Control of Small Modular Reactor Once-Through Steam Generator Based on Differential Evolution Optimization Algorithm","authors":"Wei Guo, Bo Shi, Tao Zhang, Zhijiang Wu, Guohua Xiong, Minjun Peng","doi":"10.1080/00295450.2024.2368973","DOIUrl":"https://doi.org/10.1080/00295450.2024.2368973","url":null,"abstract":"The pressure control of once-through steam generator (OTSG) is critical for the operation and safety of small modular reactors. However, the dynamics of the OTSG are quite nonlinear, time varying, ...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"39 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-07-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141744672","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Nuclear Reactor Operations Education and Training with Virtual Reality and an Immersive Desktop Application 利用虚拟现实和沉浸式桌面应用程序开展核反应堆运行教育和培训
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-18 DOI: 10.1080/00295450.2024.2368980
Shikha Prasad, Oscar L. Delgado, Alexander Tucker, Sunay Palsole
{"title":"Nuclear Reactor Operations Education and Training with Virtual Reality and an Immersive Desktop Application","authors":"Shikha Prasad, Oscar L. Delgado, Alexander Tucker, Sunay Palsole","doi":"10.1080/00295450.2024.2368980","DOIUrl":"https://doi.org/10.1080/00295450.2024.2368980","url":null,"abstract":"A virtual reality learning module to train nuclear engineering students in reactor operations to understand reactor power excursions has been developed. The learning module was taught with an Oculu...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"39 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-07-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141744673","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Processes and Interactions of Potential Relevance for Deep Geological Disposal of HLW and L/ILW at the Same Site—International Approaches and Transferability to the German Site Selection 在同一地点深层地质处置 HLW 和 L/ILW 的潜在相关过程和相互作用--国际方法及对德国选址的可借鉴性
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-17 DOI: 10.1080/00295450.2024.2368976
Marie Voss, Ute Maurer-Rurack, Andreas Poller
{"title":"Processes and Interactions of Potential Relevance for Deep Geological Disposal of HLW and L/ILW at the Same Site—International Approaches and Transferability to the German Site Selection","authors":"Marie Voss, Ute Maurer-Rurack, Andreas Poller","doi":"10.1080/00295450.2024.2368976","DOIUrl":"https://doi.org/10.1080/00295450.2024.2368976","url":null,"abstract":"As part of the German site selection procedure for deep geological disposal of high-level radioactive waste (HLW), an investigation, according to federal regulations, must be undertaken into whethe...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"17 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-07-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141744674","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Discrete Element Method Simulation of Vibratory Filling of Convoluted Hot Isostatic Pressing Canisters Using Idaho Calcine Waste Simulant 离散元素法模拟使用爱达荷州钙废模拟物对波状热等静压罐进行振动填充
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-17 DOI: 10.1080/00295450.2024.2361195
Simon Chung, Martin Stewart, Peter Wypych, David Hastie, Andrew Grima, Sam Moricca
{"title":"Discrete Element Method Simulation of Vibratory Filling of Convoluted Hot Isostatic Pressing Canisters Using Idaho Calcine Waste Simulant","authors":"Simon Chung, Martin Stewart, Peter Wypych, David Hastie, Andrew Grima, Sam Moricca","doi":"10.1080/00295450.2024.2361195","DOIUrl":"https://doi.org/10.1080/00295450.2024.2361195","url":null,"abstract":"This research presents a discrete element method (DEM) model for simulating the vibratory filling of the Idaho calcine waste simulant into various convoluted hot isostatic pressing canisters. The s...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"64 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-07-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141744675","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
A Sociotechnical Readiness Level Framework for the Development of Advanced Nuclear Technologies 开发先进核技术的社会技术就绪程度框架
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-11 DOI: 10.1080/00295450.2024.2336355
Aditi Verma, Todd Allen
{"title":"A Sociotechnical Readiness Level Framework for the Development of Advanced Nuclear Technologies","authors":"Aditi Verma, Todd Allen","doi":"10.1080/00295450.2024.2336355","DOIUrl":"https://doi.org/10.1080/00295450.2024.2336355","url":null,"abstract":"The Technology Readiness Level (TRL) scale was initially developed by the National Aeronautics and Space Administration in the 1970s and is now widely used in space, nuclear, and other complex tech...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"37 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-07-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141585806","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Numerical Simulation and Experimental Comparison of System Analysis Module 1D Mixing Model for Cold Shock Transients in the Gallium Thermal-Hydraulic Mixing Facility 镓热-水力混合设施冷冲击瞬态系统分析模块一维混合模型的数值模拟与实验比较
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-10 DOI: 10.1080/00295450.2024.2366738
Molly Ross, Ling Zou, Hitesh Bindra
{"title":"Numerical Simulation and Experimental Comparison of System Analysis Module 1D Mixing Model for Cold Shock Transients in the Gallium Thermal-Hydraulic Mixing Facility","authors":"Molly Ross, Ling Zou, Hitesh Bindra","doi":"10.1080/00295450.2024.2366738","DOIUrl":"https://doi.org/10.1080/00295450.2024.2366738","url":null,"abstract":"Liquid metals are being investigated as coolants in many advanced reactor designs because of their high thermal conductivity and effectiveness at high temperatures. However, they often pose challen...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"51 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-07-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141608844","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Analyses of Jet Buoyant Flow in a Multicompartment Containment Using an Open-Source Solver 使用开源求解器分析多室容器中的喷射浮力流
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-10 DOI: 10.1080/00295450.2024.2362527
Myeong-Seon Chae, Juwook Lee, Hyoung Kyu Cho, Stephan Kelm, Domenico Paladino
{"title":"Analyses of Jet Buoyant Flow in a Multicompartment Containment Using an Open-Source Solver","authors":"Myeong-Seon Chae, Juwook Lee, Hyoung Kyu Cho, Stephan Kelm, Domenico Paladino","doi":"10.1080/00295450.2024.2362527","DOIUrl":"https://doi.org/10.1080/00295450.2024.2362527","url":null,"abstract":"Hydrogen mixing and distribution in a nuclear power plant containment during a postulated severe accident is a phenomenon with high safety relevance for current and advanced light water reactors. T...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"78 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-07-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141608816","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Network Graph Laplacian-Based Sensor Projection in System-Level Modeling of Liquid-Metal Loop 液态金属回路系统级建模中基于网络图拉普拉斯传感器投影的研究
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-08 DOI: 10.1080/00295450.2024.2361182
Andres Gomez, Molly Ross, Hitesh Bindra
{"title":"Network Graph Laplacian-Based Sensor Projection in System-Level Modeling of Liquid-Metal Loop","authors":"Andres Gomez, Molly Ross, Hitesh Bindra","doi":"10.1080/00295450.2024.2361182","DOIUrl":"https://doi.org/10.1080/00295450.2024.2361182","url":null,"abstract":"Accurate modeling of nuclear reactor transients is important for improving operation and maintenance planning strategies in advanced reactors. An adequate understanding of the connectivity between ...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"45 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-07-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141608845","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
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