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 …

Advanced liquid-metal thermal-hydraulic research for MYRRHA

K Van Tichelen, G Kennedy, F Mirelli, A Marino… - Nuclear …, 2020 - Taylor & Francis
Abstract The Belgian Nuclear Research Centre (SCK• CEN) is at the forefront of heavy liquid-
metal (HLM) nuclear technology worldwide with the development of the Multi-purpose …

RANS simulations for transition and turbulent flow regimes in wire-wrapped rod bundles

O Bovati, MA Yildiz, Y Hassan, R Vaghetto - … Journal of Heat and Fluid Flow, 2021 - Elsevier
Internal flows through rod assemblies are commonly found in heat exchangers, steam
generators, and nuclear reactors. One of the fuel assembly designs considered for liquid …

Analysis of flow-induced vibration of wire-wrapped fuel assemblies under the liquid metal axial flow in the Gen-IV nuclear reactor

H Guo, W Li, J Zhang, Y Wu, M Wang, S Qiu… - Annals of Nuclear …, 2023 - Elsevier
Fluid excitation force is the root cause of flow-induced vibration in the fast reactor core,
which is an important cause of nuclear fuel failure and breakage phenomena. In this study …

Analysis of the turbulent flow in a partially blocked wire-wrapped rod bundle using LES with wall functions

O Bovati, Y Hassan - International Journal of Heat and Fluid Flow, 2022 - Elsevier
One of the most promising nuclear reactor designs is the Liquid-Metal Fast Reactor (LMFR).
Its fuel assembly consists of rods containing the fuel material, arranged in a triangular lattice …

Validating RANS to predict the flow behavior in wire-wrapped fuel assemblies

D Dovizio, B Mikuž, A Shams, F Roelofs - Nuclear Engineering and Design, 2020 - Elsevier
Liquid metal fast reactors (LMFRs) represent one of the most promising technologies in
terms of sustainability, safety and reduction of nuclear waste and are expected to play a …

Validation and uncertainty quantification of multiphase-CFD solvers: A data-driven Bayesian framework supported by high-resolution experiments

Y Liu, X Sun, NT Dinh - Nuclear Engineering and Design, 2019 - Elsevier
The two-fluid model-based Multiphase Computational Fluid Dynamics (MCFD) solvers are
promising tools for a variety of engineering problems related to multiphase flows. Such a …

Direct numerical simulation of fluid flow in a 5x5 square rod bundle

A Kraus, E Merzari, T Norddine, O Marin… - International Journal of …, 2021 - Elsevier
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 …

Direct numerical simulation of turbulent forced and mixed convection of LBE in a bundle of heated rods with P/D= 1.4

D Angeli, A Fregni, E Stalio - Nuclear Engineering and Design, 2019 - Elsevier
In this work, reference data obtained by means of Direct Numerical Simulations of fully-
developed flow and heat transfer around a vertical rod bundle are presented. Finite-Volume …

Liquid metal thermal hydraulics: State-of-the-art and future perspectives

F Roelofs - Nuclear Engineering and Design, 2020 - Elsevier
The energy consumption worldwide will increase for the coming decades. In order to
address global warming, international experts agree that no low CO 2 emitting energy …