Latest research progress for LBE coolant reactor of China initiative accelerator driven system project
L Gu, X Su - Frontiers in Energy, 2021 - Springer
China's accelerator driven subcritical system (ADS) development has made significant
progress during the past decade. With the successful construction and operation of the …
progress during the past decade. With the successful construction and operation of the …
Liquid metals as efficient high‐temperature heat‐transport fluids
Liquid metals appear to be attractive heat‐transport fluids, in particular if looking at their high
thermal conductivities and low viscosities. Despite some pioneering technical applications in …
thermal conductivities and low viscosities. Despite some pioneering technical applications in …
[HTML][HTML] Numerical simulation of three-dimensional flow and heat transfer characteristics of liquid lead–bismuth
S He, M Wang, J Zhang, W Tian, S Qiu… - Nuclear Engineering and …, 2021 - Elsevier
Liquid lead-bismuth cooled fast reactor is one of the most promising reactor types among the
fourth-generation nuclear energy systems. The flow and heat transfer characteristics of lead …
fourth-generation nuclear energy systems. The flow and heat transfer characteristics of lead …
Numerical study on conjugate heat transfer characteristics of liquid lead-bismuth eutectic and supercritical carbon dioxide in a PCHE straight channel
XK Su, XW Li, XY Wang, QJ Chen, QW Shi, J Qiu… - Annals of Nuclear …, 2023 - Elsevier
Abstract The Printed Circuit Heat Exchanger (PCHE) is the optimal heat transfer structure of
the fourth-generation advanced Lead–Bismuth Eutectic (LBE) cooled fast reactor coupling …
the fourth-generation advanced Lead–Bismuth Eutectic (LBE) cooled fast reactor coupling …
Numerical investigation on heat transfer characteristics of liquid metal cross flow over tube bundles
Abstract Helical tube Once Through Steam Generator (OTSG) could further improve the
compactness of liquid metal cooled reactors. The heat transfer characteristics of liquid metal …
compactness of liquid metal cooled reactors. The heat transfer characteristics of liquid metal …
Coupling heat transfer study of liquid sodium and supercritical carbon dioxide in a PCHE straight channel based on a four-equation model
XK Su, XW Li, XY Wang, QJ Chen, QW Shi, J Qiu… - Annals of Nuclear …, 2023 - Elsevier
The Brayton cycle using supercritical carbon dioxide (S-CO 2) as the working fluid is
expected to be a thermo-power conversion technology for sodium-cooled fast reactors …
expected to be a thermo-power conversion technology for sodium-cooled fast reactors …
Exploration of high-efficiency heat transfer modes in lead-cooled assemblies: A structural optimization based on the SST k-ω-kθ-ɛθ model
J Wu, X Su, Z Gong, J Cai, L Gu - Applied Thermal Engineering, 2024 - Elsevier
Accurately simulating the flow and heat transfer in a compact assembly is a critical concern
in the core design of the lead-cooled fast reactor. The key to numerical heat transfer lies in …
in the core design of the lead-cooled fast reactor. The key to numerical heat transfer lies in …
Thermofluidic modeling and temperature monitoring of Li-ion battery energy storage system
F Tao, W Zhang, D Guo, W Cao, L Sun… - Applied Thermal …, 2020 - Elsevier
The battery energy storage system (BESS) is widely used in the power grid and renewable
energy generation. With respect to a lithium-ion battery module of a practical BESS with the …
energy generation. With respect to a lithium-ion battery module of a practical BESS with the …
Investigation on the applicability of turbulent-Prandtl-number models in bare rod bundles for heavy liquid metals
Z Ge, J Liu, P Zhao, X Nie, M Ye - Nuclear Engineering and Design, 2017 - Elsevier
The study of turbulent heat transfer in heavy liquid metals has been undertaken till now as
promising coolants for advanced nuclear fast reactors. However, the low Prandtl number …
promising coolants for advanced nuclear fast reactors. However, the low Prandtl number …
Thermal-hydraulic study in a wire-wrapped 19-rod bundle based on an isotropic four-equation model
XK Su, XW Li, L Zhang, L Gu, DJ Fan - Annals of Nuclear Energy, 2022 - Elsevier
The thermal–hydraulic performance of rod bundles with wire spacers is significant for
studying Lead–Bismuth Eutectic (LBE) cooled fast reactor. The problem is that using the …
studying Lead–Bismuth Eutectic (LBE) cooled fast reactor. The problem is that using the …