Review of thermal-hydraulic issues and studies of lead-based fast reactors
Y Zhang, C Wang, Z Lan, S Wei, R Chen, W Tian… - … and Sustainable Energy …, 2020 - Elsevier
The lead-based reactor is one of the fourth-generation nuclear energy systems with
excellent development prospects. It has attracted much attention because of its unique …
excellent development prospects. It has attracted much attention because of its unique …
CorTAF-LBE: A full scale subchannel-level thermal-hydraulic characteristics analysis code for LBR core based on OpenFOAM
K Liu, J Yu, H Qiu, M Wang, W Tian, GH Su - Progress in Nuclear Energy, 2024 - Elsevier
The lead-bismuth cooled fast reactor core adopts box-type design, and the fuel rod bundle is
fixed by wrapping wires. The complex geometric structure of the fuel assemblies significantly …
fixed by wrapping wires. The complex geometric structure of the fuel assemblies significantly …
[图书][B] Nuclear systems volume I: Thermal hydraulic fundamentals
NE Todreas, MS Kazimi - 2021 - taylorfrancis.com
Nuclear Systems, Volume I: Thermal Hydraulic Fundamentals, Third Edition, provides an in-
depth introduction to nuclear power, focusing on thermal hydraulic design and analysis of …
depth introduction to nuclear power, focusing on thermal hydraulic design and analysis of …
Experimental study of heavy-liquid metal (LBE) flow and heat transfer along a hexagonal 19-rod bundle with wire spacers
J Pacio, M Daubner, F Fellmoser, K Litfin… - Nuclear Engineering and …, 2016 - Elsevier
An experimental campaign considering a 19-pin hexagonal rod bundle with wire spacers,
cooled by forced-convective LBE was completed at the Karlsruhe Liquid Metal Laboratory …
cooled by forced-convective LBE was completed at the Karlsruhe Liquid Metal Laboratory …
Heat transfer on HLM cooled wire-spaced fuel pin bundle simulator in the NACIE-UP facility
I Di Piazza, M Angelucci, R Marinari… - … Engineering and Design, 2016 - Elsevier
The NACIE-UP experimental facility at the ENEA Brasimone Research Centre (Italy) allowed
to evaluate the heat transfer coefficient of a wire-spaced fuel bundle cooled by lead-bismuth …
to evaluate the heat transfer coefficient of a wire-spaced fuel bundle cooled by lead-bismuth …
Experimental investigation on flow and heat transfer characteristics of lead–bismuth eutectic in circular tubes
Y Zhang, C Wang, R Cai, Z Lan, Y Shen… - Applied Thermal …, 2020 - Elsevier
Flow and heat transfer characteristics of LBE are of significant importance for the thermal-
hydraulic and safety analysis of lead-based fast reactors (LFRs). In this paper, an …
hydraulic and safety analysis of lead-based fast reactors (LFRs). In this paper, an …
Heat transfer to liquid metals with empirical models for turbulent forced convection in various geometries
W Jaeger - Nuclear Engineering and Design, 2017 - Elsevier
This paper gives a summary of liquid metal properties and empirical models for thermal-
hydraulic investigations. Liquid metals are used as coolant in nuclear and fusion energy and …
hydraulic investigations. Liquid metals are used as coolant in nuclear and fusion energy and …
Thermal-hydraulic study of the LBE-cooled fuel assembly in the MYRRHA reactor: Experiments and simulations
Heavy liquid metals (HLMs), such as lead-bismuth eutectic (LBE) and pure lead are
prominent candidate coolants for many advanced systems based on fast neutrons. In …
prominent candidate coolants for many advanced systems based on fast neutrons. In …
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 …
reactors to enhance the capability of flow and heat transfer. The detailed 3D thermal …
Numerical and experimental analysis of LBE flow and heat transfer characteristics in hexagonal rod bundles
X Zhou, D Zhang, J Liu, C Lin, Y Liang, W Tian… - Annals of Nuclear …, 2023 - Elsevier
Lead-bismuth eutectic (LBE) is a liquid with low Prandtl number and high thermal
conductivity, generally used as the coolant in lead-cooled fast reactors of Generation-IV. The …
conductivity, generally used as the coolant in lead-cooled fast reactors of Generation-IV. The …