袁园

    发布时间:2021.06.28

    来源: 本站

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    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月至今在物理学院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.