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 …

Flow characteristics within an interior subchannel of a 61-pin wire-wrapped hexagonal rod bundle with a porous blockage

C Menezes, T Melsheimer, DW Pyle, M Kinsky… - Physics of …, 2023 - pubs.aip.org
Potential accumulation of undesirable debris in a subchannel of a Liquid Metal Fast Reactor
(LMFR) hexagonal fuel bundle presents accident conditions, which are crucial to investigate …

LES and URANS study on turbulent flow through 3× 3 rod bundle with spacer grid and mixing vanes using spectral element method

H Ju, H Yu, M Wang, M Zhao, W Tian, T Liu… - Annals of Nuclear …, 2021 - Elsevier
In this paper, the turbulent flow in rod bundles with spacer grid and mixing vanes in nuclear
reactor core was studied using spectral element method with large eddy simulation (LES) …

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 …

Numerical study on the thermal hydraulic characteristics in a wire-wrapped assembly of LFRs

J Li, D Fang, C Guo, M Wang, J Deng… - Frontiers in Energy …, 2020 - frontiersin.org
The concept of wire-wrapped assembly has been widely adopted in liquid metal-cooled
reactors to enhance the capability of flow and heat transfer. The detailed 3D thermal …

Study on the flow and heat transfer characteristics of liquid sodium in a hexagonal 7-rod bundle

S He, M Wang, Y Hou, W Tian, S Qiu, GH Su - Nuclear Engineering and …, 2022 - Elsevier
The flow and heat transfer characteristics of liquid metal sodium are different from the
ordinary fluids, which brings great challenges to the CFD simulation in the sodium-cooled …

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 …

Fast reactor thermal hydraulics in the Dutch PIONEER program

F Roelofs, H Uitslag-Doolaard, K Zwijsen… - … Engineering and Design, 2023 - Elsevier
The multi-year research program carried out by NRG and funded by the Dutch ministry of
economic affairs and climate is called 'Program for Innovation and cOmpetence …

Experiments and CFD simulations of the LBE loop in HYST: A new concept for irradiation experiments in a fast-reactor-like environment

R Kong, S Kim, R Wahlen, J Pike, T Grimm - Nuclear Engineering and …, 2022 - Elsevier
The current work investigates the thermal-hydraulics of a HYbrid fast/thermal core
configuration Subcritical Testbed (HYST), a new concept proposed for irradiation …

SESAME project: advancements in liquid metal thermal hydraulics experiments and simulations

M Tarantino, F Roelofs, A Shams, A Batta… - EPJ N-Nuclear …, 2020 - cea.hal.science
Liquid metal cooled reactors are envisaged to play an important role in the future of nuclear
energy production because of their possibility to use natural resources efficiently and to …