● Department of Engineering Physics,Tsinghua University,Ph.D.,1996-1999,Nuclear Energy Science and Engineering.

● Department of Engineering Physics,Tsinghua University,M.S.,1994-1996,Nuclear Energy Science and Engineering.

● Department of Engineering Physics,Tsinghua University,B.S.,1989-1994,Utilization of Nuclear Energy and Thermal Energy.

● 08/2009-present: Associate Professor, Engineering Physics Department, Tsinghua University.

● 08/2008-07/2009:Visiting Scholar, Nuclear Engineering Department of University of California, Berkeley.

● 12/2004-07/2008:Associate Professor, Engineering Physics Department, Tsinghua University.

● 04/1999-11/2004:Lecturer, Engineering Physics Department, Tsinghua University.

● 05/2000-06/2000: Visiting Scholar, Obninsk Institute of Nuclear Power Engineering and Research Institute Krylov Shipbuilding.

● Nuclear Reactor Thermal Hydraulics, senior undergraduate course.

● Nuclear Reactor Systems and Operations, senior undergraduate course.

● Matlab Programming,, undergraduate course.

● Nuclear psychology, undergraduate course.

● Numerical Method of Thermal Hydraulics, graduate course.

● Nuclear Reactor Engineering, graduate course.

● Accident Analysis of Nuclear Power Plant, graduate course.

Thermal hydraulics, safety and operation of nuclear reactor.

● Basic Research on key scientific issues of supercritical water reactor -- Research on the state 973 Program of dynamic behavior of supercritical water reactor under complex working conditions

● Super critical subchannel analysis program development, AECL international cooperation

●  Supercritical water reactor research platform for the construction

● Thorium based fuel fourth generation advanced reactor development, international cooperation with AECL

● Plate element reactor core and direct current evaporator optimization calculation and nuclear power plant optimization calculation software research

● The design of horizontal cooperation with thorium based fuel assembly test

● Nuclear power plant safety in the case of hydrogen behavior

● Computational fluid dynamics analysis program developed in severe accidents, international cooperation in France

● Research on the key issues of ADS system based on the evolution of MA, the independent research program of Tsinghua University

● Large-scale advanced pressurized water reactor passive containment transient thermal analysis program

● Joint research on thermal hydraulics and neutron physics, EDF international cooperation

● Small and safe shell distribution of hydrogen concentration and uncertainty analysis

● Regulator multi zone non equilibrium model for studying

● High performance computing platform traffic distribution research

● CFR600 demonstration of steam generator and heat exchanger design

● Research of high level foreign graduate training program in the field nuclear power

● Journal Papers

　1.Yu, Jiyang; Jia, Baoshan. PCCSAC: A Three-Dimensional Code for AC600 Passive Containment Cooling System Analysis. Nuclear Science and Engineering. 142(2), 230-236. 2002.

　2.Yu, Jiyang; Wang, Kan; etc. Thorium Fuel Cycle of a Thorium-based Advanced Nuclear Energy System. Progress in Nuclear Energy. 45(1), 71-83. 2004.

　3.Yu, Jiyang; Mao, Wenlong; Jia, Baoshan; Rao, Yanfei; Ruan, Yangqiang. Thermal hydraulic analysis of the thorium-based advanced CANDU Reactor fuel channel. Progress in Nuclear Energy，V48, 559-568, 2006

　4.Yu, Jiyang; Wang, Songtao; Jia, Baoshan. Development of sub-channel analysis code for CANDU-SCWR. Progress in Nuclear Energy V49,334-350, 2007

　5.Yu, Jiyang; Liu, Haiyu; Jia, Baoshan. Sub-channel analysis of CANDU–SCWR and review of heat-transfer correlations. Progress of Nuclear Energy. 2009

　6.Yu, Jiyang; Jia, Baoshan; Wu, Dan; Wang, Daling. Optimization of heat transfer coefficient correlation at supercritical pressure using genetic algorithms. Heat Mass Transfer. 2009

　7.Gao, Lijun; Chen, Bingde; Xiao, Zhong; Jiang, Shengyao; Yu, Jiyang. Pore pressure calculation of the UO2 high burnup structure. Nuclear Engineering and Design, v 260, p 11-15, 2013

　8.ANISEH AHMEDATEF ABDALLA, JIYANG YU, YONGWEI YANG.  Thermal-hydraulic analysis of LBE spallation target for accelerator-driven systems. Pramana - Journal of Physics. 2013

　9.Dan Wu, Hongxing Yu, Junchong Yu, Jiyang Yu. Reflooding characteristics investigation and predicted models improvement for the pressurized water reactor with the tight lattice core design. Nuclear Engineering and Design, Volume 249, August 2012, Pages 335-347.

● Selected Conference Proceedings

　1.Yu, Jiyang; You, Songbo; Jia, Baoshan. A Conceptual Design of Passive Containment Cooling System for Thoriumbased Advanced Nuclear System. 13th International Conference on Nuclear Engineering. ICONE13-50195. May16-20, 2005, Beijing, China.

　2.Yu, Jiyang; Liu, Haiyu.Thermal Hydraulic Effects of Thorium Loading Mode of CANFLEX Fuel Bundle. International Workshop on Thorium Utilization for Sustainable Development of Nuclear Energy (TU2007), 4-6 December 2007, Beijing, China

　3.Yu, Jiyang; Wang, Songtao; Jia, Baoshan. Development of Sub-channel Analysis Code for CANDU-SCWR. The 3rd International Symposium on Supercritical Water-Cooled Reactors – Design and Technology -Shanghai Jiao Tong UniversityShanghai, China. March 12-15, 2007

　4.Yu, Jiyang; Peterson, Per F. Utilization of Thorium in the PB-AHTR. 2009 International Workshop on Thorium Utilization for Sustainable Nuclear Energy . September 2-6, 2009, Baotou, Inner Mongolia, China

　5.Saeed, M.; Yu, Jiyang; Hou, B.X.; Abdalla, Aniseh A. A.; Zhang, Chunhui. Numerical simulation of hydrogen dispersion inside a compartment using HYDRAGON code. International Conference on Nuclear Engineering, Proceedings, ICONE, v 4, 2016, 2016 24th International Conference on Nuclear Engineering, ICONE 2016

　6.Hou, Bingxu; Yu, Jiyang; Sénéchal, Dorothée; Min, Jiesheng; Méchitoua, Namane; Chen, Guofei. CFD simulation with code-saturne of the light gas stratification erosion by a vertical air gas injection using a low Mach number algorithm. International Conference on Nuclear Engineering, Proceedings, ICONE, v 2015-January, 2015, ICONE 2015 - 23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy

　7.Aniseh A. A. Abdalla;Jiyang Yu;Mohammad Alrwashdeh. APPLICATION OF SOME TURBULENCE MODELS TO SIMULATE BUOYANCYDRIVEN FLOW. 2014.Proceedings of the 2014 22nd International Conference on Nuclear Engineering ICONE22. July 7-11, 2014, Prague, Czech Republic

　8.Ran Li, Jiyang Yu. Development of pccsap-3D code for the analysis of passive containment performance. Proceedings of the 20th International Conference on Nuclear Engineering ICONE20. July 30 - August 3, 2011, Anaheim, California, USAJiyang Yu*, Shuwei Che, Ran Li, Bingxue Qi. Analysis of Ledinegg flow instability in natural circulation at supercritical pressure. Progress in Nuclear Energy 53 (2011)

　9.Jiyang Yu, Rui Niu. Analysis of Ledinegg Flow Instability in Natural Circulation at Supercritical Pressure. NUTHOS-8 International Topical Meeting on Nuclear Reactor Thermal Hydraulics Operation and Safety, October 10-14, 2010, Shanghai, China

　10.Abdalla, Aniseh A.A.; Yu, Jiyang; Zhang, C.H.; Hou, B.X.; Saeed, M. Investigation of the influence of turbulence models on the simulation of the gas distribution. International Conference on Nuclear Engineering, Proceedings, ICONE, v 2015-January, 2015, ICONE 2015 - 23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy.

● Books

　1.Jiyang Yu, Baoshan Jia. Reactor thermal hydraulics. Tsinghua University Press. 2003 978-7-302-06133-5 ISBN.

　2.Baoshan Jia, Jiyang Yu, Minjun Peng. Design and optimization of nuclear power plant. Press of Harbin Engineering University. 2010 978-7-811-33843-0 ISBN.

　3.Jiyang Yu, Baoshan Jia. Reactor thermal hydraulics (Second Edition). Tsinghua University press. 2011 978-7-302-26609-9 ISBN.

　4.Choi, J.-H., Gupta, S.K., Kim, H.-T., Kim, K., Krause, M., Ottaviani, A., Rao, R.S., Singhal, M., Yu, Jiyang. Comparison of Heavy Water Reactor Thermalhydraulic Code Predictions with Small Break LOCA Experimental Data. the International Atomic Energy Agency publications. Vienna 2012 ISBN:978-92-0-133710-8.

　5.Jiyang Yu, Erjun Yu. Accident analysis of nuclear power plant. Tsinghua University Press. 2012 978-7-302-29502-0 ISBN.

　6.Jiyang Yu. Thermal fluid numerical calculation. Tsinghua University press. 2013 ISBN 978-7-302-30819-5.

　7.Jiyang Yu. Nuclear psychology. Tsinghua University press. 2015 ISBN:9787302396772.

　8.Jiyang Yu. Fundamental principles of nuclear engineering. Tsinghua University press. 2016 ISBN:9787302433453.

　9.Jiyang Yu. Nuclear power plant system and operation. Tsinghua University press. 2016 ISBN:9787302450153.

● 06/1999-07/2001: Principal Member, Passive Containment Cooling System (PCCS) of AC600 Research Group.

● 12/2001-present: Administrative Program Manager, Thorium-based Advanced CANDU Reactor (TACR) Research Group, joint project with AECL.

● 07/2007-present: Key Member, Development of superciritical water reactor supported by the National Basic Research Program of China (973 Program).

● 10/2007-present: Member, RD14M ICSP of IAEA, Comparison of Simulation Results for Small-Break Loss-of-Coolant Accidents (SB LOCA) in Heavy Water Reactors.

● 01/2007-present: Committeeman, Speciality Committee of Nuclear Reactor Thermal Hydraulics of China Nuclear Energy Association (CNEA).

§2001:Best Teacher Award of Tsinghua University.

§2002:Teaching Achievement Award of Tsinghua University.

§2002-2008:AECL Scholarship in Tsinghua University (every year).

§2013:Tsinghua University teaching advanced individual.

§2014:Beijing outstanding trade union workers.

§2015:Advanced workers of the Chinese Nuclear Society.