. Chuntian Gao, Pan Wu, Jianqiang Shan , Yanping Huang, Jibin Zhan , Lianjie Wang . Preliminary study of system design and safety analysis methodology for supercritical carbon dioxide Brayton cycle direct-cooled reactor system , Annals of Nuclear Energy , 2020

. Ge Li, Lu Tianyu, Shan Jianqiang, Liu Dong . Application of a 3D model in the transient system analysis of sodium-cooled fast reactor , Annals of Nuclear Energy , 2019

. Yuan Yuan, Jianqiang Shan, Li Wang, Xiaoying Zhang . Control and thermal analysis for SCWR startup , Annals of Nuclear Energy , 2019 , 134 : 27–37

. ZijiangYang, ZhuoranDang, XiaohongYang, MamoruIshii, Jianqiang Shan . Downward two phase flow experiment and general flow regime transition criteria for various pipe sizes , International Journal of Heat and Mass Transfer , 2018 , 125 : 179-189

. ZijiangYang, JianqiangShan, JunliGou, MamoruIshii . SGTR analysis on CPR1000 with a passive safety system , Nuclear Engineering and Design , 2018 , 332 : 319-328

. Fei Chao , Jianqiang Shan, , Junli Gou, Pan Wu, Li Ge . Study on the algorithm for solving two-fluid seven-equation two-pressure model , Annals of Nuclear Energy , 2018 , Volume 111 : 379–390

. Junli Gou; Haifu Ma; Zijiang Yang; Jianqiang Shan . An assessment of heat transfer models of water flow in helically coiled tubes based on selected experimental datasets , Annals of Nuclear Energy , 2017 , Volume 110 : 648-667

. Pan Wu; Yuan Yuan; Junjie Pan; Jianqiang Shan . The stability-analysis code FIAT development for density wave oscillations and its application to PV/PT SCWR , Annals of Nuclear Energy , 2017 , Volume 110 : 833-846

. Pan Wu, Fei Chao, Dan Wu, Jianqiang Shan, and Junli Gou . Implementation and Comparison of High-Resolution Spatial Discretization Schemes for Solving Two-Fluid Seven-Equation Two-Pressure Model , Science and Technology of Nuclear Installations , 2017 , 2017 : Article ID 4252975, 14 pages

. Li Ge, Wei Liu, and Jianqiang Shan . Development and Application of a New High-Efficiency Sparse Linear System Solver in the Thermal-Hydraulic System Analysis Code , Science and Technology of Nuclear Installations , 2017