Experimental investigation of turbulent flow characteristics in cross-flow planes of a 5× 5 rod bundle with a spacer grid

CF Matozinhos, GCQ Tomaz, T Nguyen… - International Journal of …, 2021 - Elsevier
This study summarizes experimental investigations of the flow field characteristics in the
cross-flow planes of a 5× 5 rod bundle with spacer grid and split-type mixing vanes. Under …

Flow Loss Analysis and Structural Optimization of Multiway Valves for Integrated Thermal Management Systems in Electric Vehicles

M Li, S Zheng, M Wei - Energies, 2023 - mdpi.com
The multiway valve is the core component of the integrated thermal management system in
an electric vehicle, and its heat transfer loss and pressure loss significantly impact the …

Experimental study of gas-liquid flow patterns and void fraction in prototype 5× 5 rod bundle channel using wire-mesh sensor

S Liu, L Liu, H Gu, K Wang - Annals of Nuclear Energy, 2022 - Elsevier
In this paper, the wire-mesh sensor (WMS) has been successfully introduced into a typical
pressurized water reactor (PWR) prototype 5× 5 rod bundle channel. Combined with the …

Development of a correlation for mixed convection heat transfer in rod bundles

J Li, Y Xiao, H Gu, D Liu, Q Zhang - Annals of Nuclear Energy, 2021 - Elsevier
A correlation is developed to predict mixed convection heat transfer of water flow in rod
bundles. The rod bundles are 5× 5 and the Re number ranges from 1× 10 3 to 3× 10 4 in the …

Two-group bubble interfacial area concentration correlation for upward bubbly to churn flows in vertical rod bundle flow channels

X Han, G Duan, J Wang - International Journal of Heat and Mass Transfer, 2023 - Elsevier
The detailed understanding and accurate modeling of the upward two-phase flows in
vertical rod bundle flow channels are significant for various industrial applications, such as …

Experimental study on flow resistance and phase distribution of gas-liquid flow in helical cruciform fuel assembly

Q Zhang, H Wang, J Li, Q Ren, Y Zhang, Y Zhou… - Annals of Nuclear …, 2025 - Elsevier
The helical cruciform fuel (HCF) is characterized by self-supporting and enhanced
transverse mixing, which may replace the cylindrical fuel in commercial light water reactor …

Evaluation of existing correlations and development of a new correlation for single-phase friction factor in rod bundle assembly

VS Chalgeri, X Shen, T Yamamoto - Annals of Nuclear Energy, 2024 - Elsevier
Single-phase water flow in rod bundles plays a crucial role in removing the heat generated
in the nuclear reactor core. The design and safety analysis of light-water nuclear reactors …

棒束弯曲对子通道内空气-水两相流动的影响研究

李潘潇, 孙皖, 周文雄, 马在勇, 张卢腾… - 核科学与工程, 2022 - epjournal.csee.org.cn
深刻理解棒束弯曲子通道在相态特性分布和流动特性演化方面的机制对反应堆的安全设计与
分析具有重要意义. 本研究对四种不同闭合度(0%, 50%, 80% 和100%) 的棒弯曲子通道进行建 …

Radiation Transmission Imaging Applications for Nuclear Reactor Systems

J Diaz - 2022 - deepblue.lib.umich.edu
Computational advancements in the past couple of decades have propelled the capabilities
to design, model, and benchmark nuclear reactor systems. However, the lack of high …

METERO-V experimental set-up: presentation and first results. Uniform flows through a 8x34 PWR-type rod bundle with mixing grids at Reynolds number ranging from …

C Melin, G Bernard-Michel, B Cariteau… - ICAPP 2023-2023 …, 2023 - cea.hal.science
We present the METERO-V set-up and preliminary results from the first set of experiments
performed. METERO-V is a closed loop, equipped with a test section made of two halves of …