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Analysis of a Selected Experiment of the OSU-MASLWR Test Facility Regarding Heat Transfer in Helically Coiled Steam Generators Using AC2-ATHLET 对 OSU-MASLWR 试验设施中使用 AC2-ATHLET 的螺旋卷绕蒸汽发生器传热的部分试验进行分析
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-09-13 DOI: 10.1080/00295450.2024.2377027
Julia Krieger, Marco K. Koch
Research regarding small modular reactors (SMRs) is increasingly receiving attention due to the advanced stage of development of several SMR concepts. Especially, integral pressurized water reactor...
由于若干小型模块化反应堆(SMR)概念的发展已进入高级阶段,有关小型模块化反应堆(SMR)的研究正日益受到关注。特别是整体式压水反应堆...
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引用次数: 0
Code Validation of SAM Using Forced and Natural Circulation Data from NACIE-UP Benchmark 使用 NACIE-UP 基准的强制和自然环流数据对 SAM 进行代码验证
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-09-04 DOI: 10.1080/00295450.2024.2377526
Victor Coppo Leite, Elia Merzari, Ling Zou
Heavy liquid metals (HLMs) are promising candidates as coolants of Generation IV fast reactors due to their thermophysical properties. In the last decade, experimental work has been proposed as par...
重液态金属(HLMs)因其热物理性质而有望成为第四代快堆的冷却剂。在过去的十年中,实验工作已提出将重金属作为第四代快堆冷却剂的一部分。
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引用次数: 0
Comparative Study of Raman and EPMA Elemental Mapping of an Unirradiated MOX Sample 未受辐照 MOX 样品的拉曼和 EPMA 元素图谱对比研究
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-09-04 DOI: 10.1080/00295450.2024.2377012
Jean-Yves Colle, Philipp Pöml, Jacobus Boshoven, Rudy J. M. Konings
The distribution of U and Pu of a mixed-oxide fuel sample is analyzed by Raman spectroscopy and electron probe microanalysis, with the goal of comparing the distribution maps from the two technique...
通过拉曼光谱和电子探针显微分析,分析了混合氧化物燃料样品中铀和钚的分布,目的是比较两种技术的分布图。
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引用次数: 0
Verification and Demonstration of One-Dimensional Freezing Model in SAM for Salt-Cooled Reactor Analysis Applications 盐冷反应器分析应用 SAM 中一维冻结模型的验证和演示
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-08-30 DOI: 10.1080/00295450.2024.2377522
Ling Zou, Quan Zhou, Dan O’Grady, Rui Hu, Alex Heald, Haihua Zhao
This work presents the development and implementation of the one-dimensional freezing model in system analysis code SAM (System Analysis Module), code verification using analytical solutions, and c...
这项工作介绍了系统分析代码 SAM(系统分析模块)中一维冻结模型的开发和实施、使用分析解决方案的代码验证,以及系统分析代码 SAM(系统分析模块)中二维冻结模型的开发和实施。
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引用次数: 0
Advancing Fixed-Source Reactor Analysis Through OpenNode Implementation 通过 OpenNode 实现推进固定源反应堆分析
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-08-29 DOI: 10.1080/00295450.2024.2385795
Hicham Satti, Otman El Hajjaji, Tarek El Bardouni, Mohamed Mira, Abdelhamid Nouayti
OpenNode, a new open-source Fortran code, enables the simulation of fixed-source reactors. Powered by the nodal expansion method (NEM) and seamless Python integration, OpenNode competes with existi...
OpenNode 是一种新的开源 Fortran 代码,可用于固定源反应堆的仿真。OpenNode 采用节点扩展法 (NEM),并与 Python 无缝集成,可与现有的 NEM 软件竞争。
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引用次数: 0
High-Fidelity Simulation of the Light-to-Dense Stratification Transient in the HiRJET Facility 在 HiRJET 设施中高保真模拟轻-密层析瞬态
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-08-23 DOI: 10.1080/00295450.2024.2382621
Cheng-Kai Tai, Haomin Yuan, Elia Merzari, Igor A. Bolotnov
Density stratification in a large enclosure is a crucial phenomenon to heat transfer and sustainable passive heat removal of a sodium fast reactor during reactivity transients. However, engineering...
在反应瞬态期间,大型围壳内的密度分层是钠快堆传热和可持续被动散热的关键现象。然而,工程...
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引用次数: 0
Neutronics and Thermo-Fluids Simulation of Generic Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor 通用卵石床氟化盐冷却高温反应堆的中子学与热流体模拟
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-08-13 DOI: 10.1080/00295450.2024.2381282
Jin Li, Thomas Downar, Volkan Seker, Dan O’Grady, Rui Hu, Nader Satvat, Shai Kinast
The fluoride-salt-cooled high-temperature reactor (FHR) is one of the advanced reactors that has been attracting considerable interest from both the research community and the nuclear industry. To ...
氟化盐冷却高温反应堆(FHR)是研究界和核工业界都十分关注的先进反应堆之一。为了 ...
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引用次数: 0
Simulation and Mitigation of False Data Injection Cyberattacks on a Space Nuclear Reactor Power System 模拟和缓解对空间核反应堆动力系统的虚假数据注入网络攻击
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-08-13 DOI: 10.1080/00295450.2024.2380952
Mohamed S. El-Genk, Timothy M. Schriener
This paper investigates the response of the DynMo-CBC space nuclear reactor power system to simulated cybersecurity attacks during a startup transient and demonstrates the effectiveness of the miti...
本文研究了 DynMo-CBC 空间核反应堆动力系统在启动瞬态期间对模拟网络安全攻击的响应,并展示了该系统的有效性。
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引用次数: 0
Numerical Simulation of Steam Jet Condensation Through a Triple Nozzle Submerged into a Subcooled Water Pool 通过浸没在过冷水池中的三喷嘴进行蒸汽喷射冷凝的数值模拟
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-08-13 DOI: 10.1080/00295450.2024.2385217
Lei Wu, Jianjun Wang, Zhongning Sun
Submerged steam jet condensation is widely applied in many industrial fields due to its high heat and mass transfer efficiency during the process of direct contact condensation (DCC). The injection...
由于在直接接触冷凝(DCC)过程中具有较高的传热和传质效率,浸没式蒸汽喷射冷凝被广泛应用于许多工业领域。喷射式蒸汽冷凝是一种新型的冷凝技术。
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引用次数: 0
Determining the Position of Gamma-Ray Interaction Using Large Scintillation Detectors and the Least Number of Photomultiplier Tubes 利用大型闪烁探测器和最少的光电倍增管确定伽马射线相互作用的位置
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-08-12 DOI: 10.1080/00295450.2024.2385796
Hadi Shahabinejad
Determining the position of interaction is of great interest for gamma-ray imaging in various nuclear applications. Among all gamma-ray detectors, scintillation detectors are commonly exploited for...
确定相互作用的位置对各种核应用中的伽马射线成像具有重大意义。在所有伽马射线探测器中,闪烁探测器通常用于...
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引用次数: 0
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Nuclear Technology
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