Education

Ph. D,  Tsinghua University, Nuclear Engineering, 1989

M.S., Tsinghua University, Nuclear Engineering, 1986

B.S. , Tsinghua University, Automobile Engineering, 1983

Work Experience

12/2003-present, Research Professor, Division of Reactor Thermal Hydraulics, INET

12/1995-11/2003, Research Associate Professor, Division of Reactor Thermal Hydraulics, INET

06/1996-07/1998, Post-D., KAERI, Korea

12/1989-11/1995, Research Assistant Professor, Division of Reactor Thermal Hydraulics, INET

Areas of Research Interests/ Research Projects

Since 1989, Dr. Jia has been engaged in experimental and theoretical research on nuclear reactor engineering and safety, thermal hydraulics, two-phase flow stability, and nuclear seawater desalination. In 1995, Dr. Jia participated in a cooperative research on heating reactors at the Kurchatov Nuclear Research Center in Russia. From 1996 to 1998, Dr. Jia worked as a postdoctoral researcher and invited expert at the Korea Atomic Energy Research Institute (KAERI), where he conducted theoretical research on  flow instability in natural circulation nuclear heating reactors. The research report was included in the NTIS database of U.S. government research reports. In 2003, as the chief scientific investigator from China, Dr. Jia participated in the International Atomic Energy Agency (IAEA)’s cooperative research on “Optimal Coupling of Nuclear Reactors and Desalination Systems.” The research report was officially published by the IAEA in 2005.  

Dr. Jia has participated in more than ten national key projectsover the years. Dr. Jia has supervised over ten graduate students, published more than 50 research papers, about 20 of which have been indexed by SCI, EI, and ISTP, and have won second and third prizes in scientific and technological progress from ministerial and commission-level authorities.

Research Status

2023-2025  Experiment research and equipment design on nuclear reactor engineering and safety, including steam consumption device, titanium heat transfer tube seawater scaling test etc.

Selected Academic Achievement

Zhang Zuoyi, Zhang Yayun, Jia Haijun, Key Technologies of Low-temperature Nuclear Heating Reactor, Shanghai Jiao Tong University Press, Shanghai, 2023.

LIU Yang，JIA Hai-jun，WU Lei，Scaling Analysis and Design for Integrated Nuclear Heating ReactorⅡMajor Loop Test Facility Under Single Phase Natural Circulation, Atomic Energy Science and Technology, V01.46, Suppl. Dec. 2012.

Academician Gao Congjie (Jia Haijun, Chapter 4), Desalination of Seawater and the Development of the Utilization Seawater and Brackish Water, Higher Education Press,  Beijing, July 2007.

Jia, H. (one of contributors) , Optimization of the coupling of nuclear reactors and desalination systems, IAEA-TECDOC-1444, ISBN 92–0–102505–X, ISSN 1011–4289, © IAEA, Vienna, Austria, June 2005

Jia, HJ, Song, JH, Experimental and theoretical study on density wave instability in low quality natural circulation loop, Korea Atomic Energy Research Institute, Taejon (Korea, Republic of). 31 Jul 1997. 100p. Report: KAERI/TR-917/97, DE98622137,