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 …

Numerical analysis of the three-dimensional flow phenomena in a 19-pin wire-wrapped tight lattice bundle

J Li, Y Xiao, G Ding, Z Xiong, H Gu - International Journal of Heat and Mass …, 2022 - Elsevier
The wire-wrapped tight lattice assembly has the advantages of compact arrangement, small
volume, and high power density, and it has been widely used in the design of advanced …

Flow visualization on SFR wire-wrapped 19-pin bundle geometry using MIR-PIV-PLIF and comparisons with RANS-based CFD analysis

MS Song, JH Jeong, ES Kim - Annals of Nuclear Energy, 2020 - Elsevier
In this study, measurement of turbulence intensity, pressure drop and local velocity field in
the sodium fast reactor (SFR) wire-wrapped 19-pin bundle have been conducted to compare …

Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part II: Evaluation of public experimental data

J Pacio, SK Chen, YM Chen, NE Todreas - Nuclear Engineering and …, 2022 - Elsevier
This two-part paper presents an updated version of the long term MIT-NTHU modeling effort
on the hydraulics of hexagonal arrays of wire wrapped fuel pins. It has been stimulated by …

Flow field characteristics of a 127-pin rod bundle with hexagonal spacer grids

C Menezes, T Melsheimer, YA Hassan - Physics of Fluids, 2023 - pubs.aip.org
A determination of nominal flow phenomena in liquid metal fast reactor (LMFR) fuel
assemblies is critical toward generation-IV reactor development. Axially positioned spacer …

Numerical investigation on characteristics of the onset of nucleate boiling in petal-shape fuel rod bundle assembly

L Du, Z Jiang, W Zhang, J Sun, G Jin, W Cai - Annals of Nuclear Energy, 2024 - Elsevier
The helical structure of the petal-shape fuel element results in a high heat transfer
performance. Therefore, it is crucial to analyze its thermal–hydraulic characteristics …

Investigation of pressure loss and velocity distribution in fuel assemblies with wire-wrapped rods by using RANS and LES with wall functions

U Bieder, H Uitslag-Doolaard, B Mikuž - Annals of Nuclear Energy, 2021 - Elsevier
Hexagonal assemblies of wire wrapped fuel rods were analyzed experimentally at Texas
A&M University. CFD analysis with LES and RANS (SST k-ω) of a 61-pins experiment have …

Flow analysis in a 37-pin wire-wrapped rod bundle for sodium-cooled fast reactor using magnetic resonance velocimetry. I. Validation and gross behavior

C Im, K Seo, JH Cho, I Jang, S Song - Physics of Fluids, 2024 - pubs.aip.org
The sodium-cooled fast reactor (SFR), a fourth-generation nuclear reactor, utilizes liquid
sodium as a coolant and offers advantages like operation at atmospheric pressure and the …

High‐Fidelity Numerical Investigation on Elucidating Sodium Heat Transfer Characteristics for 37‐Pin Wire‐Wrapped Fuel Bundle in the PLANDTL Facility

G Choi, S Yoon, M Song… - International Journal of …, 2023 - Wiley Online Library
This study involved a Reynolds‐averaged Navier‐Stokes‐(RANS‐) based computational
fluid dynamics (CFD) analysis of the 37‐pin wire‐wrapped fuel bundle of the PNC Plant …

Flow analysis in a 37-pin wire-wrapped rod bundle for sodium-cooled fast reactor using magnetic resonance velocimetry. II. Detailed characterization and influence of …

C Im, K Seo, JH Cho, I Jang, S Song - Physics of Fluids, 2024 - pubs.aip.org
In Paper I, we presented comprehensive three-dimensional, three-component (3D, 3C)
mean velocity profiles obtained through magnetic resonance velocimetry (MRV) within a 37 …