A review of sub-channel thermal hydraulic codes for nuclear reactor core and future directions
Thermal hydraulic analysis of nuclear reactor core is mainly performed using the sub-
channel analysis codes to estimate different thermal hydraulic safety margins. The safety …
channel analysis codes to estimate different thermal hydraulic safety margins. The safety …
From discovery to recognition of periodic large scale vortices in rod bundles as source of natural mixing between subchannels—a review
L Meyer - Nuclear Engineering and Design, 2010 - Elsevier
The mixing of cooling fluid in rod bundles from one subchannel to another through the gaps
between the rods reduces the temperature differences in the coolant as well as along the …
between the rods reduces the temperature differences in the coolant as well as along the …
Challenges in low-Prandtl number heat transfer simulation and modelling
G Grötzbach - Nuclear engineering and design, 2013 - Elsevier
Nuclear heat transfer applications with low-Prandtl number fluids are often in the transition
range between conduction and convection dominated regimes. Most flows in reactors …
range between conduction and convection dominated regimes. Most flows in reactors …
Thermal hydraulic considerations of nuclear reactor systems: Past, present and future challenges
GH Yeoh - Experimental and Computational Multiphase Flow, 2019 - Springer
Thermal hydraulic analysis of nuclear reactor core and its associated systems can be
performed using analysis system, subchannel or computational fluid dynamics (CFD) codes …
performed using analysis system, subchannel or computational fluid dynamics (CFD) codes …
Quasi-DNS capabilities of OpenFOAM for different mesh types
Experimental limitations for certain nuclear reactor safety applications have pushed forward
the demand for high fidelity DNS reference solutions for complex geometric configurations …
the demand for high fidelity DNS reference solutions for complex geometric configurations …
[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 …
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 …
Analysis of low Reynolds number turbulent flow phenomena in nuclear fuel pin subassemblies of tight lattice configuration
This paper focuses on the numerical simulation of low Reynolds (Re) number turbulence
flow phenomena in tightly packed fuel pin subassemblies and in channels of irregular shape …
flow phenomena in tightly packed fuel pin subassemblies and in channels of irregular shape …
Effect of stochastic deformation on the vibration characteristics of a tube bundle in axial flow
H Dolfen, S Vandewalle, J Degroote - Nuclear Engineering and Design, 2023 - Elsevier
Abstract Design evaluation of nuclear components using numerical methods has typically
been focused on nominal geometries and conditions. In reality, the geometry of reactor …
been focused on nominal geometries and conditions. In reality, the geometry of reactor …
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 …