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Development of a New Correlation for Saturated Flow Boiling Heat Transfer in a Helically Coiled Tube 螺旋卷管内饱和流沸腾传热新相关性的开发
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-04-12 DOI: 10.1080/00295450.2024.2319926
Min Gi Kim, Byongjo Yun, Jae Jun Jeong
We have developed a heat transfer correlation for saturated flow boiling of water in a helically coiled tube. Initially, we collected experimental data encompassing a broad spectrum of thermal-hydr...
我们开发了螺旋卷管内水饱和流沸腾的传热相关性。起初,我们收集的实验数据涵盖了广泛的热-水-传热系数。
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引用次数: 0
Two-Fluid and Discrete Population Balance Model for Simulation of Batch Sedimentation Relevant to Plutonium Reconversion 模拟与钚再转化有关的批量沉积的双流体和离散种群平衡模型
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-04-12 DOI: 10.1080/00295450.2024.2326714
Saroj Kumar Panda, Panantharayil Vishnu Anand, Vivek Kumar Mishra, Ramachandran Pillai Rajeev, Konda Athmaram Venkatesan, Krishnamurthy Ananthasivan
There are widespread occurrence and application of solid-liquid sedimentation processes among different industries. Therefore, it becomes important to understand the hydrodynamic inside the process...
固液沉淀工艺在各行各业都有广泛的应用。因此,了解过程内部的流体力学变得非常重要。
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引用次数: 0
Calculation and Discussion for Crack Driving Force of Dissimilar Metal Welded Joint of Nuclear Power Equipment Nozzle and Safe End 核电设备喷嘴与安全端异种金属焊接接头裂纹驱动力的计算与讨论
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-04-12 DOI: 10.1080/00295450.2024.2329833
Dasheng Wang, Jin Ting, Xu Xiao, Tan Jianping, Zhang Kun, Wang Guozhen
This study investigates the effects of the material mechanical properties heterogeneity and strength mismatch variation on crack driving forces for cracks in a dissimilar metal welded joint (DMW) o...
本研究探讨了材料机械性能异质性和强度失配变化对异种金属焊接接头(DMW)裂纹驱动力的影响。
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引用次数: 0
Adsorption of Radioactive Iodine Using Nanocarbon on ETS-10 as Adsorbent 使用 ETS-10 上的纳米碳作为吸附剂吸附放射性碘
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-04-12 DOI: 10.1080/00295450.2024.2329834
Chaithanya Balumuru, Krishnan Raja, Piyush Sabharwall, Vivek Utgikar
Laboratory-synthesized nanocarbon pelletized with titanosilicate (ETS-10) as a support matrix has been investigated for the capture of radioactive iodine present as methyl iodide (CH3I) in the off-...
研究了实验室合成的以钛硅酸盐(ETS-10)为支撑基质的纳米碳颗粒,用于捕获离体中以甲基碘(CH3I)形式存在的放射性碘。
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引用次数: 0
Exploring the Feasibility of Kuiper Belt Missions Supported by Centrifugal Nuclear Thermal Propulsion 探索由离心核热推进器支持的柯伊伯带飞行任务的可行性
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-04-12 DOI: 10.1080/00295450.2024.2323242
William Ziehm, L. Dale Thomas
Missions to the Kuiper belt have previously been carried out only as flybys and with very small payloads. Investigating launch windows for Kuiper belt missions supported by centrifugal nuclear ther...
以前对柯伊伯带的飞行任务只能以飞越的方式进行,而且有效载荷非常小。对由离心核热处理器支持的柯伊伯带任务的发射窗口进行调查...
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引用次数: 0
Progress in Fast Modular Reactor Conceptual Design 快速模块化反应堆概念设计的进展
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-04-11 DOI: 10.1080/00295450.2024.2319925
Hangbok Choi, John Bolin, Oscar Gutierrez, Radu Curiac, Mohammad Alavi, Matthew Virgen, Ed Chin, James Beaver, Pascal Brocheny, Geoffrey Beausoleil, Abdellatif M. Yacout, Sal Rodriguez, Michael Corradini, Daejong Kim, Steven L. Krahn, Eric Thornsbury
The Fast Modular Reactor (FMR) is a 100-MW(thermal) gas-cooled fast reactor being developed by General Atomics Electromagnetic System with the goal of developing a FMR for flexible and dispatchable...
快速模块化反应堆(FMR)是通用原子电磁系统公司(General Atomics Electromagnetic System)正在开发的一种100兆瓦(热)气冷快堆,其目标是开发一种用于灵活调度的快速模块化反应堆。
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引用次数: 0
Novel Approach for Network Data Exchange Among Safety-Related Control Systems of Nuclear Reactors 核反应堆安全相关控制系统之间网络数据交换的新方法
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-04-11 DOI: 10.1080/00295450.2024.2325749
Aditya Gour, R. P. Behera, Tom Mathews
Industrially mature digital networking technologies form the backbone of the distributed control architectures of nuclear reactors. Typically, hundreds of control systems responsible for assuring s...
工业上成熟的数字网络技术是核反应堆分布式控制架构的支柱。通常情况下,数以百计的控制系统负责确保核反应堆的安全。
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引用次数: 0
A Study on Boiling Heat Transfer Performance of TiO2-CNTs Hybrid Nanofluid on a Downward-Facing Heating Surface TiO2-CNTs 混合纳米流体在朝下加热表面上的沸腾传热性能研究
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-04-11 DOI: 10.1080/00295450.2024.2323240
Songling Liu, Huai-En Hsieh, Shiqi Wang
In-vessel retention through external reactor vessel cooling (IVR-ERVC) is a strategy used to respond to nuclear reactor accidents. One of the key performance indicators determining its feasibility ...
通过外部反应堆容器冷却(IVR-ERVC)进行舱内保留是一种用于应对核反应堆事故的策略。决定其可行性的关键性能指标之一 ...
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引用次数: 0
Creep Fatigue Analysis of the 316SS Monolith in the MegaPower Heat Pipe Reactor 兆瓦级热管反应堆中 316SS 单体的蠕变疲劳分析
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-04-11 DOI: 10.1080/00295450.2024.2310902
Yong Wang, Lichuang Liang, Jun Tian, Dongchuan Su, Hui Li, Naibin Jiang
The heat pipe reactor represents a promising high-temperature microreactor design comprising heat pipes, fuel rods, and monoliths. Prolonged operation at elevated temperatures leads to an obvious t...
热管反应堆是一种很有前途的高温微反应器设计,由热管、燃料棒和整体组成。在高温条件下长期运行会导致明显的...
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引用次数: 0
Mixing of Hydrogen-Steam Buoyancy Jets Released into the Upper Atmosphere of the Containment Building 释放到安全壳大楼高层大气中的氢气-蒸汽浮力射流的混合情况
IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-04-11 DOI: 10.1080/00295450.2024.2325738
Youngsu Na
This study evaluates the spatial dilution of hydrogen concentration caused by steam-hydrogen buoyancy jets rising through the open top of the steam generator compartment during a loss-of-coolant ac...
本研究评估了在失去冷却剂的情况下,蒸汽-氢气浮力射流通过蒸汽发生器舱的敞开顶部上升所造成的氢气浓度的空间稀释。
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引用次数: 0
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Nuclear Technology
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