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 …
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 …
A quantification method for numerical dissipation in quasi-DNS and under-resolved DNS, and effects of numerical dissipation in quasi-DNS and under-resolved DNS …
LES for industrial applications with complex geometries is mostly characterised by: a) a finite
volume CFD method using a non-staggered arrangement of the flow variables and second …
volume CFD method using a non-staggered arrangement of the flow variables and second …
Development of a flow sweeping mixing model for helical fuel rod bundles
Y Xiao, J Fu, Q Zhang, H Zhao, H Gu - Annals of Nuclear Energy, 2021 - Elsevier
The helical fuel rod is a kind of axially twisted fuel element with a three or four-petaled
profile. The helical fuel rod assembly assembled by helical fuel rods against one another in …
profile. The helical fuel rod assembly assembled by helical fuel rods against one another in …
Interface tracking simulations of bubbly flows in PWR relevant geometries
The advances in high performance computing (HPC) have allowed direct numerical
simulation (DNS) approach coupled with interface tracking methods (ITM) to perform high …
simulation (DNS) approach coupled with interface tracking methods (ITM) to perform high …
Computational fluid dynamics (CFD) round robin benchmark for a pressurized water reactor (PWR) rod bundle
SK Kang, YA Hassan - Nuclear Engineering and Design, 2016 - Elsevier
This study examined the capabilities and limitations of steady Reynolds-Averaged Navier–
Stokes (RANS) approach for pressurized water reactor (PWR) rod bundle problems, based …
Stokes (RANS) approach for pressurized water reactor (PWR) rod bundle problems, based …
Direct numerical simulation of fluid flow in a 5x5 square rod bundle
Abstract Characterization of parallel flow through rod bundles is of key importance in
assessing the performance and safety of several engineering systems, including a majority …
assessing the performance and safety of several engineering systems, including a majority …
CFD simulation of swirling flow induced by twist vanes in a rod bundle
Swirling flow induced by the twist vanes can enhance the heat transfer in the rod-bundle fuel
assembly. In order to investigate accuracy of the k-ε models in predicting the swirling flow in …
assembly. In order to investigate accuracy of the k-ε models in predicting the swirling flow in …
On the use of (U) RANS and LES approaches for turbulent incompressible single phase flows in nuclear engineering applications
S Benhamadouche - Nuclear Engineering and Design, 2017 - Elsevier
The present paper gives some ideas and guidelines in order to run high quality (U) RANS or
LES computations. The paper starts with (U) RANS approaches, advocating the use of …
LES computations. The paper starts with (U) RANS approaches, advocating the use of …