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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 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-08-06 DOI: 10.1080/00295639.2024.2383099
Kristel Ghoos, Lukas Zavorka, Joseph Tipton, Igor Remec
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...
美国能源部橡树岭国家实验室的第二靶站(STS)正在设计中,它将成为世界上峰值亮度最高的中子源。
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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 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-08-06 DOI: 10.1080/00295639.2024.2380611
Adam Q. Lam, Richard M. Vega
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...
我们提出了一种求解线性玻尔兹曼输运方程的新方法。求解偏微分方程的两种常用且广为人知的方法是特征法和线性波尔兹曼输运方程法。
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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 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-08-06 DOI: 10.1080/00295639.2024.2383110
Rafael Isayev, Natalia Pukhareva, Evgeniy Malinovskiy, Egor Korenevski, Pavel Dzhumaev
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...
结构材料与铅和铅铋共晶的兼容性是开发使用重型液态金属冷却剂的快中子反应堆所面临的重大挑战。液态金属冷却剂与铅和铅铋共晶的相容性是开发使用重液态金属冷却剂的快中子反应堆的重大挑战。
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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 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-08-06 DOI: 10.1080/00295639.2024.2380607
Colin A. Weaver, Christopher M. Perfetti, Michael E. Rising
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...
为辐射输运代码 MCNP6.3 开发了一个数值代码库,用于计算固定源中子输运问题的广义响应灵敏度系数,并将其应用于...
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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 Q3 NUCLEAR SCIENCE & TECHNOLOGY 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
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...
正在积极开发核微反应器的研究人员正计划采用创新设计和功能,而传统的商业建模工具可能无法满足他们的需求。
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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 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-08-02 DOI: 10.1080/00295639.2024.2372516
Wanyi Tian, Yanfei Zhang, Weiwei Chen, Junhao Zhang, Bingyu Ni, Chao Jiang
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...
根据国际原子能机构关于尽量减少放射性废料的要求,核设施部件需要切割成小块,并用废料箱包装。
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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 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-08-02 DOI: 10.1080/00295639.2024.2370675
D. Ghasemabadi, H. Zaki Dizaji, M. Abdollahzadeh
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...
这项研究旨在调查和分析用于光伏电池的最佳β放射性同位素,重点是提高光伏电池的性能和效率。我们进行了...
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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 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-08-02 DOI: 10.1080/00295639.2024.2375174
Hossam H. Abdellatif, David Arcilesi
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...
AP1000 电站的创新设计包含多层被动安全系统,旨在提高反应堆在正常和瞬态条件下的安全性。被动安全壳冷却系统...
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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 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-08-02 DOI: 10.1080/00295639.2024.2372515
Andy Rivas, Gregory Kyriakos Delipei, Jason Hou
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 ...
先进反应堆设计人员希望最大限度地提高系统容量因子,使先进反应堆更具经济竞争力,并满足预计的能源需求。为了实现这一目标,我们 ...
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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 Q3 NUCLEAR SCIENCE & TECHNOLOGY 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
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...
温度分布在处置高放射性废物的深层地质处置库的安全性能评估和热尺寸设计中起着至关重要的作用。在这项研究中,采用了一种...
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引用次数: 0
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Nuclear Science and Engineering
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