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 …
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 …
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
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 …
(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 …
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
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 …
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
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 …
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 …
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 …
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
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 …
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
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 …
program has been investigating the behavior of high-burnup fuel during design basis …