含氦氙混合气体的螺旋楔形燃料组件的中子学和热液特性数值分析

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2024-11-12 DOI:10.1016/j.nucengdes.2024.113688

Wenxuan Ju , Kewei Ning , Lin Xie , Fulong Zhao , Sichao Tan

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引用次数: 0

摘要

螺旋楔形燃料因其优异的热和水力特性而被用于新型反应堆的研究。研究人员对由螺旋锥形燃料和氦-氙（He-Xe）混合气体组成的 3 × 3 燃料组件的中子、流动和传热特性进行了数值模拟。通过轴向差分和几何重构实现了燃料棒的高精度建模，分析了功率分布特性，获得了 HCF 成分的速度和温度分布，并研究了边界层特性。计算结果表明，轴向功率密度呈余弦分布。螺旋楔形燃料迎风面和背风面的速度边界层厚度存在明显差异，迎风面粘滞子层的相应速度是背风面的 1.38-2.72 倍。迎风面的表面传热系数更大。

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Numerical analysis of Neutronics and Thermal-Hydraulic properties of Helical-Cruciform fuel assembly with Helium-Xenon gas mixture

Helical-cruciform fuel is researched in new reactors due to its excellent thermal and hydraulic properties. A numerical simulation was conducted on the neutron, flow, and heat transfer characteristics of a 3 × 3 fuel assembly composed of helical-cruciform fuel with a Helium-Xenon (He-Xe) gas mixture. High-precision modeling of fuel rods was achieved through axial differential and geometric reconstruction, the power distribution characteristics were analyzed, the velocity and temperature distribution of HCF components were obtained, and the boundary layer properties were investigated. The calculation results show that the axial power density presents a cosine distribution. A significant difference appears in the velocity boundary layer thickness between the windward and leeward sides of the helical-cruciform fuel, the corresponding velocity of the viscous sublayer on the windward side is 1.38–2.72 times higher than that on the leeward side. A larger surface heat transfer coefficient appears on the windward side.

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.