袁园，女，博士，博士后。2017年获西安交通大学核能科学与工程专业博士学位。2017年-2020年在中山大学任职特聘副研究员，2021年1月至今在bat365正版唯一官网核工程与核技术系工作。

研究方向

核反应堆热工水力与安全分析，反应堆系统设计

代表性论文或成果

[1].Yuan Yuan, Jianqiang Shan*, Xiaoying Zhang, Li Wang. Accident analysis of supercritical water reactors during startup[J]. Progress in Nuclear Energy, 2020(121): 1-15.

[2].Yuan Yuan, Jianqiang Shan, Li Wang*, Xiaoying Zhang. Control and thermal analysis for SCWR startup[J]. Annals of Nuclear Energy, 2019(134): 27-37.

[3].Yuan Yuan*, Jianqiang Shan, Li Wang, Dongqing Wang, Xiaoying Zhang. Startup thermal analysis of a supercritical-pressure light water-cooled reactor CSR1000, Frontiers in Energy Research, 2018(6): 1-12.

[4].Yuan Yuan, Jianqiang Shan, Bin Zhang*, Junli Gou, Bo Zhang, Tianyu Lu, Li Ge, Zijiang Yang. Study on startup characteristics of heat pipe cooled and AMTEC conversion space reactor system. Progress in Nuclear Energy, 2016 (86): 18-30.

[5].Yuan Yuan, Jianqiang Shan, Bin Zhang*, Junli Gou, Bo Zhang, Tianyu Lu, Li Ge, Zijiang Yang. Accident analysis of heat pipe cooled and AMTEC conversion space reactor system. Annals of Nuclear Energy, 2016(94): 706-715.

[6].Laishun Wang, Yuan Yuan*, Nejdet Erkan, Fengchen Li, Koji Okamoto. Effect of metal honeycomb structure on enhancing CHF in saturated downward-facing flow boiling[J]. International Journal of Heat and Mass Transfer, 2020(149): 1-4.

[7].Laishun Wang, Yuan Yuan*, Jianqing Shan, Xiaoying Zhang. Study on thermal hydraulic characteristics under startup of SCWR[J]. Progress in Nuclear Energy, 2020(122): 1-10.

[8].Laishun Wang, Yuan Yuan*, Nejdet Erkan, Haiguang Gong, Khan R. Abdul, Fengchen Li, Koji Okamoto. Influence of surface wettability increase induced by Gamma-ray irradiation on critical heat flux in downward-facing flow boiling[J]. Annals of Nuclear Energy, 2020(142): 107420.

[9].Pan Wu, Yuan Yuan, Junjie Pan, Jianqing Shan. The stability-analysis code FIAT development for density wave oscillations and its application to PV/PT SCWR[J]. Annals of Nuclear Energy 2017(101): 833-846.

[10].Yuan Yuan, Bin Zhang*, Jianqiang Shan, Junli Gou, Bo Zhang. Study on startup characteristics of heat pipe cooled space reactor, NURETH16, 2015.8.

[11].Yuan Yuan, Bin Zhang*, Jianqiang Shan, Junli Gou, Bo Zhang. Accident analysis of heat pipe cooled space reactor, NURETH16, 2015.8.

[12].Yuan Yuan, Jianqiang Shan*, Pan Wu, Bin Zhang, Junli Gou, Bo Zhang. Startup thermal analysis of a supercritical-pressure light water-cooled reactor CSR1000. NUTHOS-11, Korea. 2016.10.

[13].袁园，单建强，王丽*，王冬青，张小英. 超临界水堆全系统启动特性研究[J]. 核动力工程, 2019, 40(5): 13-17.

[14].袁园，王丽*，罗涵禹，单建强，张小英，王冬青. CSR1000启动过程控制特性研究，核动力工程,  2019, 40(3)：115-120.

[15].袁园，苟军利，单建强*，张斌，张博. 热管冷却空间反应堆系统启动特性研究，原子能科学技术, 2016, 50 (6): 1054-1059.

[16].刘松涛*，袁园，魏宗岚，曾未，朱力，苟军利. 热管冷却空间反应堆事故特性研究，核动力工程, 2016，37(5): 119-124.