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 …

Building a multiscale framework: An overview of the NEAMS thermal-hydraulics integrated research project

E Merzari, I Bolotnov, N Dinh, E Baglietto… - … Engineering and Design, 2025 - Elsevier
GPU-based supercomputing enables a significant advancement in Computational Fluid
Dynamics (CFD) capabilities for nuclear reactors. Pre-exascale GPU-based supercomputers …

Experimental characterization of pressure and friction factor in an interior subchannel of a 61-pin wire-wrapped rod bundle with a porous blockage

C Menezes, M Kinsky, DW Pyle, YA Hassan - Physics of Fluids, 2023 - pubs.aip.org
Comprehending and counteracting accident conditions presented by impedances of flow in
diminutive subchannels of a Liquid Metal Fast Reactor (LMFR) hexagonal rod bundle are …

Feasibility of full-core pin resolved CFD simulations of small modular reactor with momentum sources

J Fang, DR Shaver, A Tomboulides, M Min… - … Engineering and Design, 2021 - Elsevier
Complex flow structure interactions and heat transfer processes take place in nuclear
reactor cores. Given the extreme pressure/temperature and radioactive conditions inside the …

Subchannel analysis–Current practice and development for the future

BW Yang, H Ninokata, J Long, A Liu, B Han - Nuclear Engineering and …, 2021 - Elsevier
Major progress in subchannel analysis development and application are reviewed in this
paper with focus mainly on the computational schemes, model improvements (including …

Sub-channel CFD for nuclear fuel bundles

B Liu, S He, C Moulinec, J Uribe - Nuclear Engineering and Design, 2019 - Elsevier
This paper presents a novel Computational Fluid Dynamics (CFD)-based sub-channel
framework for nuclear power plants, which combines the advantageous features of modern …

[HTML][HTML] A comparative analysis of detailed and reduced CFD approaches to model wire-wrapped fuel bundles for LMFBRs applications

O Halim, F Galleni, N Forgione, I Di Piazza… - Annals of Nuclear …, 2025 - Elsevier
The paper investigates the capabilities of different CFD modelling approaches in
reproducing operating conditions relevant for Liquid Metal Fast Breeder Reactors …

A porous medium model for simulating conjugate heat transfer between wire-wrapped fuel bundles under forced and mixed convection

Y Chen, Y Liang, D Zhang, S Wang, C Wang… - Annals of Nuclear …, 2021 - Elsevier
Wire-wrapped fuel bundles have been widely used in SFRs, and the conjugate heat transfer
between wire-wrapped fuel bundles plays a key role in safety characteristics of SFRs …

CFD analysis of transverse flow in a wire-wrapped hexagonal seven-pin bundle

P Zhao, J Liu, Z Ge, X Wang, X Cheng - Nuclear Engineering and Design, 2017 - Elsevier
Transverse flow induced by helical spacer wires has important effects on the flow and heat
transfer behavior of reactor core. In this paper, transverse flow in a wire-wrapped hexagonal …

Coupled Monte Carlo transport and conjugate heat transfer for wire-wrapped bundles within the MOOSE framework

AJ Novak, P Shriwise, PK Romano… - Nuclear Science and …, 2023 - Taylor & Francis
Cardinal is an open-source application that couples OpenMC Monte Carlo transport and
NekRS computational fluid dynamics (CFD) to the Multiphysics Object-Oriented Simulation …