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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
Charge Distribution Studies in the Epi-Cadmium Neutron-Induced Fission of 241Pu 外镉中子诱导 241Pu 裂变的电荷分布研究
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-07-31 DOI: 10.1080/00295639.2024.2371748
H. Naik, R. J. Singh, S. P. Dange, W. Jang
For the first time, charge distribution studies have been carried out in the epi-cadmium neutron-induced fission of 241Pu by measuring the fractional cumulative yields (FCYs) and independent yields...
通过测量分数累积产率(FCYs)和独立产率,首次对表镉中子诱导的 241Pu 裂变进行了电荷分布研究。
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引用次数: 0
Challenges and Technology-Driven Opportunities for Safeguarding Microreactors 保障微反应器安全的挑战和技术驱动的机遇
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-07-31 DOI: 10.1080/00295639.2024.2372223
Emerald D. Ryan, Ishita Trivedi, Stefano Terlizzi, Ashley Shields, Mark Schanfein, Gustavo Reyes, Ryan Stewart
Nuclear microreactors (MRs) represent a new class of reactors characterized by their compactness, portability, and low power output. These features enable MRs to supply electricity and process heat...
核微型反应堆(MR)是一类新型反应堆,其特点是结构紧凑、便于携带、输出功率低。这些特点使 MR 能够供电和制热...
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引用次数: 0
Self-Healing Control of Nuclear Power Plants Under False Data Injection Attacks 虚假数据注入攻击下的核电站自愈控制
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-07-30 DOI: 10.1080/00295639.2024.2372520
Stephen Yoo, Greg Mohler, Fan Zhang
The transition from analog to digital instrumentation and control (I&C) systems introduces new threats caused by cyberattacks in the nuclear industry. This paper proposes a self-healing strategy to...
从模拟到数字仪表与控制系统(I&C)的过渡给核工业带来了网络攻击的新威胁。本文提出了一种自愈策略,以...
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引用次数: 0
Thermal Model of the AGR-5/6/7 Experiment with Offset Gas Gaps 带有偏置气隙的 AGR-5/6/7 试验热模型
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-07-11 DOI: 10.1080/00295639.2024.2368994
Grant Hawkes, Binh Pham, Courtney Otani
Because of their high impact on calculated temperatures, the offset gas gaps between the graphite holder and capsule wall are evaluated for the thermal model of the Advanced Gas Reactor 5/6/7 (AGR-...
由于石墨支架和舱壁之间的偏移气体间隙对计算温度有很大影响,我们对先进气体反应堆5/6/7(AGR-...
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引用次数: 0
Monte Carlo Source Convergence Diagnosis Method and Thermal-Physics Coupling Method Based on Functional Expansion Tallies 基于函数展开式的蒙特卡罗源收敛诊断方法和热物理耦合方法
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-07-10 DOI: 10.1080/00295639.2024.2363575
Nan An, Xiaoyu Guo, Hao Luo, Zhaoyuan Liu, Kan Wang
In iterative Monte Carlo calculations for nuclear reactors, the inactive cycles should be calculated first to ensure that the source distribution is converged, and then the tallies of various param...
在核反应堆的迭代蒙特卡洛计算中,应首先计算非活动循环,以确保源分布收敛,然后计算各种参数的总和。
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引用次数: 0
Examining Beam Matching in the Commissioning of a Halcyon Accelerator 在 Halcyon 加速器调试过程中检查光束匹配情况
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-07-01 DOI: 10.1080/00295639.2024.2366733
Duong Thanh Tai, Hoang Duc Tuan, Nguyen Xuan Hai, Nguyen Ngoc Anh, David Bradley, Peter Sandwall, James C. L. Chow
This study aims to describe the steps needed to be made in developing a commissioning report of a Halcyon linear accelerator utilizing the manufacturer’s golden beam data (GBD) as a reference in ma...
本研究旨在描述利用制造商提供的黄金光束数据(GBD)作为参考,编写 Halcyon 直线加速器调试报告所需的步骤。
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引用次数: 0
Review and Modeling of Integrated Energy Systems with Nuclear Reactor Coupled Desalination and District Heating 核反应堆耦合海水淡化和区域供热综合能源系统回顾与建模
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-07-01 DOI: 10.1080/00295639.2024.2357394
Md Akhlak Bin Aziz, C. T. Callaway, Nicholas R. Brown, Caleb Brooks
Detailed reviews of a past advanced nuclear reactor–based integrated energy system, as well as other nuclear reactor and fossil fuel–based integrated energy systems, have been performed for this wo...
本研究对过去基于先进核反应堆的综合能源系统以及其他基于核反应堆和化石燃料的综合能源系统进行了详细审查。
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引用次数: 0
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Nuclear Science and Engineering
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