A review of CFD studies on thermal hydraulic analysis of coolant flow through fuel rod bundles in nuclear reactor

M Wang, H Ju, J Wu, H Qiu, K Liu, W Tian… - Progress in Nuclear …, 2024 - Elsevier
Fuel pins assembled in Pressurized Water Reactor (PWR) and Liquid Metal-cooled Fast
Reactor (LMFR) core are usually cooled by single-phase coolant such as water or liquid …

Review of interdisciplinary heat transfer enhancement technology for nuclear reactor

Q Lu, Y Liu, J Deng, X Luo, Z Deng, Z Mi - Annals of Nuclear Energy, 2021 - Elsevier
All over the world, the nuclear reactor technology has been in the critical stage of
transformation and upgrading. Also, there have been the higher requirements for the key …

Flow characteristics within an interior subchannel of a 61-pin wire-wrapped hexagonal rod bundle with a porous blockage

C Menezes, T Melsheimer, DW Pyle, M Kinsky… - Physics of …, 2023 - pubs.aip.org
Potential accumulation of undesirable debris in a subchannel of a Liquid Metal Fast Reactor
(LMFR) hexagonal fuel bundle presents accident conditions, which are crucial to investigate …

Experimental measurement of bubbly two-phase flow in a 4x4 rod bundle with wire mesh sensor

J Xiong, H Xie, S Du, X Cheng - Applied Thermal Engineering, 2023 - Elsevier
In order to investigate two-phase bubbly flow through fuel assembly of pressurized water
reactor (PWR), the wire mesh sensor (WMS) is employed to measure air-water flow in a up …

[HTML][HTML] Turbulent flow characteristics in an 84-pin rod bundle for typical and damaged spacer grids

C Menezes, AD Carroll, CF Matozinhos, R Vaghetto… - Physics of …, 2022 - pubs.aip.org
Hexagonal rod bundles arranged in a tightly packed triangular lattice are extensively used
for heat transfer and energy generation applications. Staggered spacer grids are used to …

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 …

Experimental study of coherent structures downstream mixing vaned spacer grid of different inclination angles in a 5× 5 rod bundle by TR-PIV

W Qu, H Xie, D Shen, Z Wang, J Xiong - Annals of Nuclear Energy, 2023 - Elsevier
Experimental study of coherent structures downstream of a spacer grid with different
inclination angles (20°, 25°, 30°) of split-type mixing vanes in a 5× 5 rod bundle was …

Numerical investigation of the effect of mixing vanes on subcooled boiling in a 3× 3 rod bundle channel with spacer grid

P Yang, T Zhang, L Hu, L Liu, Y Liu - Energy, 2021 - Elsevier
Mixing vane grids (MVGs) are an integral part of nuclear reactor fuel assembly, and
significantly impact the flow and heat transfer characteristics of the coolant in a rod bundle …

Thermal hydraulic review of light water reactor based on subchannel code CTF

X Zhang, N Gui, H Gong, X Yang, J Tu… - Nuclear Engineering and …, 2023 - Elsevier
Studying thermal hydraulics in reactor cores is essential for ensuring the safe operation of
nuclear power plants and advancing the development of reactors and fuel. In the CASL …

Assessment of the CTF subchannel code for modeling a large-break loss-of-coolant accident reflood transient

R Salko, A Wysocki, B Hizoum, N Capps - Annals of Nuclear Energy, 2025 - Elsevier
With increased industry interest in extending reactor operating cycles, the neams!(neams!)
program has been investigating the behavior of high-burnup fuel during design basis …