2002 -2006, Control Science and Engineering ,Xi’an Jiaotong University, Doctor
1999 -2002, Nuclear Science and Engineering ,Xi’an Jiaotong University, Master
1995 -1999, Electrical Engineering, Xi’an Jiaotong University, Bachelor

2007-2008: Post-doctoral research, School of Nuclear Science and Engineering, Shanghai Jiao Tong University;
2009-now: Lecturer, School of Nuclear Science and Engineering, Shanghai Jiao Tong University;
2009.10-2010.03: Visiting Researcher, Department of Energy and Environment Engineering, OSAKA University, Japan.

Reactor safety;
Thermal Hydraulic of Reactor;
Instrumentation & Control systems in Nuclear Power Plant.

1. From 2018 to 2019, Deepening Research on Melt Retention in Large-scale Passive Nuclear Power Plant, supported by tne National Science and Technology Major Project , in charge of the sub-project 3: Heat Transfer in Molten Pool and CHF Experimental Research, Project Leader;
2. From 2016 to 2017, Fuel-Coolant Interaction Test Verification Project, supported by CIAE,Project Leader;
3. From 2016 to 2017, Thermal-Hydraulic Equivalent Modeling Project for PWR Nuclear Power Units, from China Electric Power Research Institute ( CEPRI), Project Leader;
4. From2015 to 2016, Expansion tests of ERVC project, from Shanghai Nuclear Engineering Research and Design Institute(SNERDI, belonging to National Science and Technology Major Project ), Project Leader;
5. rom2015 to 2016, Pipeline Material Analysis Test Platform and Pipeline Vapor-liquid Two-phase Flow Test Project, from State Nuclear Electric Power Planning Design & Research Institute (belonging to National Science and Technology Major Project ), Project Leader;
6. From 2014 to 2015, Test project for measuring the temperature field of reactor pressure vessel support, from Shanghai Nuclear Engineering Research and Design Institute(SNERDI, belonging to National Science and Technology Major Project ), Project Leader;
7. From 2011 to 2015, project of Full-height Scale Engineering Verification Test of In-vessel Molten Retention and Passive External Cooling of Reactor Pressure Vessel, supported by National Science and Technology Major Project of China, technical leader.
8. From 2011 to 2015, Development of ACPR1000 Control System Simulation Platform, supported by China Nuclear Power Engineering Co.Ltd. Project Leader;
9. From 2008 to 2011, Stability Analysis of Supercritical Water Reactor, supported by National Basic Research Program of China (973 Program), Sub-project Leader;
10. From 2007 to 2008, Research on Core Program of Full-Range Simulator Simulation Platform for Ap1000 Nuclear Power Station , supported by the Shanghai Postdoctoral Sustentation Fund, Project Leader.

Journal articles :
1． Liu Pengfei ，Hou Dong，Kuang Bo，Yang Yanhua，1-D Dynamic Stability Analysis of Mixed-Spectrum Supercritical Water Reactor Core，Annals of Nuclear Energy，2017.03，101：278-292 （SCI/EI）
2． Pengfei Liu, Chunyu Bi,Yang Yu, Meng Lin1, Xinli Song, Guoyang Wu and Zhida Su。Development of a hardware-in- loop simulation platform for NPP main control systems. MATEC Web of Conferences，2017.11,128: 02012（EI）
3． Chunyu Bi,Pengfei Liu, Xinli Song, Guoyang Wu and Zhida Su, Simulation Study and Parameter Evaluation on Water Level Control System of Steam Generator in Nuclear Power Plant, Advances in Intelligent Systems Research,2017.7，134：38-41.
4． Pengfei Liu，Dong Hou， Meng Lin， Bo Kuang. Stability analysis of parallel-channel systems under supercritical pressure with heat exchanging. Annals of Nuclear Energy 69 (2014) 267–277 (SCI/EI)
5． Dong Hou , Meng Lin, Pengfei Liu, Yanhua Yang，Stability analysis of parallel-channel systems with forced flows under supercritical pressure[J], Annals of Nuclear Energy 38 (2011) 2386–2396 (SCI/EI)
6． Meng Lin, Dong Hou, Pengfei Liu, Zongwei Yang, Yanhua Yang. Main Control System Verification and Validation of NPP Digital I&C System based on Engineering Simulator, Nuclear Engineering and Design, 2010, 240(7), 1887-1896.(SCI/ EI)
7． Pengfei Liu, Jiuqiang Han,et. Gait Synthesis Based on FWN for a Five-link Biped Robot. International Journal of Wavelets, Multi-resolution and Information Processing.2007,5(1):197-211 (SCI/EI)

Conference papers in 5 years:
1．Longkun He, Liu Pengfei *, Xisi Zhang, Wenjun Hu, Bo Kuang, Liangzhang Wei.
Experimental Study on the Interaction of Molten Sn With Water，DOI: 10.1115/ICONE26-82204，2018，London, England.
2. Haozheng Kong, Bo Kuang, Pengfei Liu, Xia Lu, Yi Yao, Lifang Liu,Bo Dong. Evaluation of IET Facility Applicability on Simulating SBLOCA in Large-Scale Passive PWR Plant, DOI: 10.1115/ICONE26-82630, 2018，London, England.
3．Fan Wang，Bo Kuang， Pengfei Liu， Longkun He. Experimental Investigation on Boiling Flow Characteristics Under Passive IVR-ERVC Conditions，DOI: 10.1115/ICONE26-82254, 2018，London, England.
4. Longkun He, Pengfei Liu*, Bo Kuang, Liangzhang Wei. Experimental study on the interaction of molten 304SS with water. NUSSA-2018, Chengdu.
5. WEI Liangzhang , LIU Pengfei*, KUANG Bo, LIN Meng. Development and validation of a hardware-in-loop NPP digital I&C system simulation platform. NUSSA-2018, Chengdu.
6. Cao Chengque, Kuang Bo, Liu Pengfei. Dynamic Stability Analysis of Supercritical Natural Circulation Loop :Frequency Domain method，2018, NUTHOS-12,Qingdao.
6. Wang Xin, Kuang Bo, Liu Pengfei，Li Yan。Analysis on Performance of Moving Body Dynamics in a Hydraulic Driven Shutdown Subassembly for Sodium Cooled Fast Reactor，12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12)，2018.10，Qingdao, China
7. Kuang B.; Liu P.F.; Wang F.; Cao K.M.; Zhang K. Influences of some engineered factors on IVR-ERVC limits. 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2017-9-3 ~ 2017-9-8, 2017
8. Pengfei Liu ，Xian Zhang, Nan Zhao, Junliang Liu, Kuang Bo，Preliminary Experimental Study on Erosion-Corrosion Behavior of Second Loop Pipeline in Nuclear Power Plant with Vapor Liquid Two Phase Flow，25rd International Conference on Nuclear Engineering（ICONE25），Shanghai，2017:ICONE25- 67762
9. Pengfei Liu, Bo Kuang. Experimental study on CHF characteristics with downward-facing curved heating surface under natural circulation condition[C], ICONE23-1925,. 23rd International Conference on Nuclear Engineering (ICONE23),Japan,2015.
10. Kuang Bo, Liu Pengfei, Fan Yunliang, Zhu Chen, Tang Chaoli, Wang Fan, Some experimental phenomena in a full-height ERVC strategy validation test facility for a large advanced PWR, Int. Workshop on Nuclear Safety and Severe Accident (NUSSA-2014),Sept. 3-5, 2014, Chiba, Japan
11. Pengfei Liu. Heat transfer to water at supercritical pressure flowing upwards in vertical tubes[C].International Meeting of Specialists in Heat Transfer to Fluids at Supercritical Pressure, Manchester, UK, 30th June/1st July 2014

1、 Course Name：Reactor Operation and Control
Teaching Target: Undergraduate students
Credit Hour：48
Credit：3
2、 Course Name：Control, Protection and Measuring system in NPP
Teaching Target: Undergraduate students
Credit Hour：32
Credit：2
3. Frontier in nuclear energy
Teaching Target: Graduate students
Credit Hour：36
Credit：2
4. Vapor-liquid two-phase flow and heat transfer
Teaching Target: Graduate students
Credit Hour：48
Credit：3

From 2013 to now, Committee member of Nuclear Energy Branch of China Electrical Engineering Society

In 2018, First Prize Winner of Nuclear Energy Industry Association;
In 2017, awarded People of the Year 2016 in Scientific Chinese;
In 2016, Second Prize Winner of Teaching Candlelight Award From University;
In 2011, Third Prize Winner of Nuclear Energy Industry Association.