Research on efficient CFD calculation and analysis technology for sodium-cooled fast reactor core
Special Issue on The First Academic Annual Conference of the Research Reactor and Innovative Reactor Association of Chinese Nuclear Society and Advanced Nuclear Power System Reactor Engineering|更新时间:2025-08-19
|
Research on efficient CFD calculation and analysis technology for sodium-cooled fast reactor core
“In the field of fourth generation nuclear reactors, experts use porous media models to analyze the thermal and hydraulic characteristics of sodium cooled fast reactor cores, providing important references for core design optimization.”
SUN Yuchen,CHEN Guangliang,ZHAO Qiang,et al.Research on efficient CFD calculation and analysis technology for sodium-cooled fast reactor core[J]. NUCLEAR TECHNIQUES,2025,48(07):070013-070013.
Influence of fine nuclide density model on neutronic characteristics in EBR-II core based on LoongSARAX
Sensitivity analysis of large leakage sodium-water reaction protection system critical parameters with paralleling steam generators in a sodium-cooled fast reactor
A CIPS risk evaluation methodology applicable for PWR
The transient analysis of molten salt reactor reactivity insertion based on RELAP5/FLUENT coupled program
Related Author
ZHANG Tengfei
LUO Chixu
LI Zikang
BAI Xi
SUN Peiwei
LUO Gang
CAO Huasong
WEI Xinyu
Related Institution
Shanghai Jiao Tong University
Xi'an Thermal Power Research Institute Co. Ltd
Nuclear Power Institute of China
School of Nuclear Science and Technology, Xi'an Jiaotong University