教育及工作经历

2000              清华大学工程物理系 学士
2003              中国原子能科学研究院 硕士
2010              美国普渡大学（Purdue University） 博士
2011-2013      美国威斯康星大学（University of Wisconsin）博士后
2013-2015      瑞士保罗谢尔研究院（Paul Scherrer Institut）研究人员
2015-今          amjs澳金沙门线路首页教授

研究方向

反应堆热工水力与安全分析
核能系统最佳估算与不确定性分析
先进反应堆非能动安全系统设计
燃料组件临界热流密度计算与分析
整体效应实验与分离效应实验及程序验证与确认（V&V）
反应堆安全过滤排放系统及放废处理

科研项目

1. 先进核能系统安全分析中的关键问题，基金委专项
2. 事故模型的模化不确定性研究，国防项目
3. 整体效应实验相关模型，企业科技项目
4. 航行器中的热物理与控制耦合研究，自主创新项目

代表性论文与专利

(1)    Deng, C., Zhang, X., Yang, Y., Yang, J*., 2019b. Research on scaling design and applicability evaluation of integral thermal-hydraulic test facilities: A review. Ann Nucl Energy 131, 273-290. [Link]

(2)    Dong, S.-c., Yang, J*., 2019. Overview of the test facilities and experimental studies and simulation research on the performance of filtered containment venting systems with wet scrubber. Ann Nucl Energy. In press.

(3)    Yang, J*., et al., Best Estimate Plus Uncertainty analysis of a large break LOCA on Generation III reactor with RELAP5. Annals of Nuclear Energy 127 (2019) pp. 326-340 [Link]

(4)    J. Yang*, D. Suckow, T. Lind And H.-M. Prasser, Study of Level Swell at VEFITA Facility for Filtered Containment Venting System, Progress of Nuclear Energy 113 (2019) pp. 7-17[Link].

(5)    Deng, C. Chen, L. Yang, J, et al., Best-estimate calculation plus uncertainty analysis of SBLOCA transient for the scale-down passive test facility. Progress in Nuclear Energy 112, (2019) pp. 191-201 [Link]

(6)    J. Yang*,Doo Yong Lee, Shuichiro Miwa, Shao-wen Chen, “Overview of filtered containment venting system in Nuclear Power Plants in Asia”, Annals of Nuclear Energy, 119 (2018), pp. 87-97 [Link]

(7)    J. Yang*, M. S. Greenwood, M. Angelis, M. Avery, M. Anderson, M. Corradini, J. Matos, F. Dunn, E. Feldman, “Study of Critical Heat Flux in Natural Convection Cooled TRIGA Reactors with Single Annulus and Rod Bundle Geometries”, Nuclear Science and Engineering, 180 (2015), pp. 1-13 [Link]

(8)    J. Yang*, J. Lim, S. W. Choi, D. Y. Lee, S. Rassame, T. Hibiki, M. Ishii, “Behaviors of Passive Safety System under a Feed Water Line Break LOCA on a Generation III+ Boiling Water Reactor”, Progress in Nuclear Energy 83 (2015)pp. 35-42 [Link]

(9)    J. Lim, J. Yang, S. W. Choi, D. Y. Lee, S. Rassame, T. Hibiki, M. Ishii*, “Assessment of Passive Safety System Performance under Gravity Driven Cooling System Drain Line Break Accident”, Progress in Nuclear Energy, 74 (2014), pp. 136-14 [Link]

(10)    J. Lim, S. W. Choi, J. Yang, D. Y. Lee, S. Rassame, T. Hibiki, M. Ishii*, “Assessment of Passive Safety System Performance under Main Steam Line Break Accident”, Annals of Nuclear Energy, 64 (2014) pp. 287-294 [Link] [Link]

(11)    S. Rassame*, M. Griffiths, J. Yang, D. Y. Lee, P. Ju, S.W. Choi, T. Hibiki, and M. Ishii, “Experimental investigation of void distribution in Suppression Pool during the initial blowdown period of a Loss of Coolant Accident using air–water two-phase mixture,” Annals of Nuclear Energy, 73 (2014) pp. 53-67  [Link]

(12)    S. Rassame*, M. Griffiths, J. Yang, D. Y. Lee, P. Ju, S.W. Choi, T. Hibiki, and M. Ishii, “Experimental Investigation of Void Distribution in Suppression Pool Over the Duration of a Loss of Coolant Accident Using Steam-Water Two-Phase Mixture,” Annals of Nuclear Energy, 75, (2014) pp. 570-580 [Link]  

(13)    J. Yang*, S. W. Choi, J. Lim, D. Y. Lee, S. Rassame, T. Hibiki, M. Ishii, “Counterpart experimental study of ISP-42 PANDA tests on PUMA facility”, Nuclear Engineering and Design, 258 (2013) pp. 249-257 [Link]

(14)    J. Yang*, S. W. Choi, J. Lim, D. Y. Lee, S. Rassame, T. Hibiki, M. Ishii, “Assessment of performance of BWR passive safety systems in a small break LOCA with integral testing and code simulation”, Nuclear Engineering and Design, 247 (2012) pp. 128-135 [Link]

(15)    M. Avery, J. Yang*, M. Anderson, M. Corradini, J. Matos, F. Dunn, E. Feldman, “Critical Heat Flux in TRIGA-Fueled Reactors Cooled By Natural Convection”, Nuclear Science and Engineering 172 (2012) pp. 249-258 [Link]

所获荣誉和奖励