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Designing the Second Target Station with a Coupled Neutronics-Mechanical Optimization Workflow 利用中子-机械耦合优化工作流程设计第二靶站
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-06 DOI: 10.1080/00295639.2024.2383099
Kristel Ghoos, Lukas Zavorka, Joseph Tipton, Igor Remec
{"title":"Designing the Second Target Station with a Coupled Neutronics-Mechanical Optimization Workflow","authors":"Kristel Ghoos, Lukas Zavorka, Joseph Tipton, Igor Remec","doi":"10.1080/00295639.2024.2383099","DOIUrl":"https://doi.org/10.1080/00295639.2024.2383099","url":null,"abstract":"The Second Target Station (STS) at the Spallation Neutron Source of the U.S. Department of Energy’s Oak Ridge National Laboratory is being designed to become the world’s highest peak brightness sou...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"22 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-08-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141932567","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
A Characteristics Approach to the Finite Element Method 有限元法的特征方法
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-06 DOI: 10.1080/00295639.2024.2380611
Adam Q. Lam, Richard M. Vega
{"title":"A Characteristics Approach to the Finite Element Method","authors":"Adam Q. Lam, Richard M. Vega","doi":"10.1080/00295639.2024.2380611","DOIUrl":"https://doi.org/10.1080/00295639.2024.2380611","url":null,"abstract":"We present a new method for solving the linear Boltzmann transport equation. Two commonly used and well-understood methods for solving partial differential equations are the method of characteristi...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-08-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141932566","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
Corrosion of EP823 Steel Cladding Under Heavy Liquid-Metal-Coolant Reactor Conditions: A Review 重型液态金属冷却剂反应堆条件下 EP823 钢包层的腐蚀：综述
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-06 DOI: 10.1080/00295639.2024.2383110
Rafael Isayev, Natalia Pukhareva, Evgeniy Malinovskiy, Egor Korenevski, Pavel Dzhumaev
{"title":"Corrosion of EP823 Steel Cladding Under Heavy Liquid-Metal-Coolant Reactor Conditions: A Review","authors":"Rafael Isayev, Natalia Pukhareva, Evgeniy Malinovskiy, Egor Korenevski, Pavel Dzhumaev","doi":"10.1080/00295639.2024.2383110","DOIUrl":"https://doi.org/10.1080/00295639.2024.2383110","url":null,"abstract":"The compatibility of structural materials with lead and lead-bismuth eutectic is a significant challenge in the development of fast neutron reactors with heavy liquid-metal coolants. Liquid-metal c...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"194 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-08-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141932618","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
Fixed Source Sensitivity Calculations for Inertial Confinement Fusion Applications 用于惯性约束聚变应用的固定源灵敏度计算
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-06 DOI: 10.1080/00295639.2024.2380607
Colin A. Weaver, Christopher M. Perfetti, Michael E. Rising
{"title":"Fixed Source Sensitivity Calculations for Inertial Confinement Fusion Applications","authors":"Colin A. Weaver, Christopher M. Perfetti, Michael E. Rising","doi":"10.1080/00295639.2024.2380607","DOIUrl":"https://doi.org/10.1080/00295639.2024.2380607","url":null,"abstract":"A numerical code library was developed for the radiation transport code MCNP6.3 to calculate generalized response sensitivity coefficients for fixed source neutron transport problems with applicati...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"101 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-08-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141932764","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
High-Fidelity Multiphysics Modeling of a Heat Pipe Microreactor Using BlueCrab 使用 BlueCrab 对热管微反应器进行高保真多物理场建模
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-05 DOI: 10.1080/00295639.2024.2375175
Nicolas E. Stauff, Yinbin Miao, Yan Cao, Kun Mo, Ahmed Amin E. Abdelhameed, Lander Ibarra, Christopher Matthews, Emily R. Shemon
{"title":"High-Fidelity Multiphysics Modeling of a Heat Pipe Microreactor Using BlueCrab","authors":"Nicolas E. Stauff, Yinbin Miao, Yan Cao, Kun Mo, Ahmed Amin E. Abdelhameed, Lander Ibarra, Christopher Matthews, Emily R. Shemon","doi":"10.1080/00295639.2024.2375175","DOIUrl":"https://doi.org/10.1080/00295639.2024.2375175","url":null,"abstract":"Researchers who are actively developing nuclear microreactors are planning to employ innovative designs and features using traditional commercial modeling tools that may be inadequate for their des...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"24 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-08-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141932873","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
A Multi-Objective Optimization Design for Enhancing Space Utilization and Minimizing Cutting Time in Nuclear Facility Component Decommissioning 核设施部件退役中提高空间利用率和缩短切割时间的多目标优化设计
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-02 DOI: 10.1080/00295639.2024.2372516
Wanyi Tian, Yanfei Zhang, Weiwei Chen, Junhao Zhang, Bingyu Ni, Chao Jiang
{"title":"A Multi-Objective Optimization Design for Enhancing Space Utilization and Minimizing Cutting Time in Nuclear Facility Component Decommissioning","authors":"Wanyi Tian, Yanfei Zhang, Weiwei Chen, Junhao Zhang, Bingyu Ni, Chao Jiang","doi":"10.1080/00295639.2024.2372516","DOIUrl":"https://doi.org/10.1080/00295639.2024.2372516","url":null,"abstract":"According to the International Atomic Energy Agency’s requirements for the minimization of radioactive waste, nuclear facility components need to be cut into smaller blocks and packaged in waste co...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"35 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-08-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141932872","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 and Analysis of Beta Radioisotopes for Optimal Use in Betavoltaic Batteries 调查和分析 Beta 放射性同位素，以优化 Betavoltaic 电池的使用
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-02 DOI: 10.1080/00295639.2024.2370675
D. Ghasemabadi, H. Zaki Dizaji, M. Abdollahzadeh
{"title":"Investigation and Analysis of Beta Radioisotopes for Optimal Use in Betavoltaic Batteries","authors":"D. Ghasemabadi, H. Zaki Dizaji, M. Abdollahzadeh","doi":"10.1080/00295639.2024.2370675","DOIUrl":"https://doi.org/10.1080/00295639.2024.2370675","url":null,"abstract":"This research aims to investigate and analyze the optimal beta radioisotopes for use in betavoltaic batteries, focusing on enhancing a betavoltaic battery’s performance and efficiency. We conducted...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"30 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-08-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141932661","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
Numerical Investigation of Air Natural Convection in the AP1000 Passive Containment Cooling System Following LBLOCA Using ANSYS FLUENT 使用 ANSYS FLUENT 对 LBLOCA 后 AP1000 被动安全壳冷却系统中的空气自然对流进行数值研究
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-02 DOI: 10.1080/00295639.2024.2375174
Hossam H. Abdellatif, David Arcilesi
{"title":"Numerical Investigation of Air Natural Convection in the AP1000 Passive Containment Cooling System Following LBLOCA Using ANSYS FLUENT","authors":"Hossam H. Abdellatif, David Arcilesi","doi":"10.1080/00295639.2024.2375174","DOIUrl":"https://doi.org/10.1080/00295639.2024.2375174","url":null,"abstract":"The innovative design of the AP1000 power plant has various layers of passive safety systems aiming to enhance reactor safety during normal and transient conditions. The passive containment cooling...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"38 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-08-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141932565","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
A System Predictive Maintenance Framework for Advanced Reactors Using a Data-Driven Digital Twin 使用数据驱动的数字孪生系统的先进反应堆系统预测性维护框架
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-02 DOI: 10.1080/00295639.2024.2372515
Andy Rivas, Gregory Kyriakos Delipei, Jason Hou
{"title":"A System Predictive Maintenance Framework for Advanced Reactors Using a Data-Driven Digital Twin","authors":"Andy Rivas, Gregory Kyriakos Delipei, Jason Hou","doi":"10.1080/00295639.2024.2372515","DOIUrl":"https://doi.org/10.1080/00295639.2024.2372515","url":null,"abstract":"Advanced reactor designers are looking to maximize the system capacity factor to make advanced reactors more economically competitive and meet the projected energy demand. To achieve this goal, we ...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"188 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-08-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141968747","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
Analytical Prediction of Temperature Distribution in a Deep Geological Nuclear Waste Repository 深层地质核废料库温度分布的分析预测
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-07-31 DOI: 10.1080/00295639.2024.2372513
Xiangyun Zhou, Shixiang Hu, Weiding Zhuo, Long Wang, De’An Sun, Luqiang He, You Gao, Xiayang Zhang
{"title":"Analytical Prediction of Temperature Distribution in a Deep Geological Nuclear Waste Repository","authors":"Xiangyun Zhou, Shixiang Hu, Weiding Zhuo, Long Wang, De’An Sun, Luqiang He, You Gao, Xiayang Zhang","doi":"10.1080/00295639.2024.2372513","DOIUrl":"https://doi.org/10.1080/00295639.2024.2372513","url":null,"abstract":"Temperature distribution plays a crucial role in the safety performance assessment and thermal dimensioning design in a deep geological repository for disposing high-level waste. In this study, a t...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"77 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-07-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141932617","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
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