Senior Research Scientist of Nuclear Science and Engineering

Division of Nuclear Safety & Environment

(+86 10) 6279-7135

Education background

PhD, Tsinghua University, Nuclear Science and Engineering, 2006
B.E., Xian Jiaotong University, Energy and Power Engineering, 2001


01/2014-present, Senior Research Scientist, Division of Nuclear Safety & Environment, INET
08/2006-12/2013, Research Scientist, Division of Nuclear Safety & Environment, INET

Social service


Reliability Engineering and Risk Analysis

Areas of Research Interests/ Research Projects

Dr Zhaos research interests are in the areas of nuclear safety analysis, especially, Probabilistic Risk Assessment (PRA).

Probabilistic Risk Assessment

The probabilistic risk assessment (PRA) of nuclear power plant (NPP) can be used to support the demonstration of safety level of NPP, and to find the weakness in the design and operation of NPP. Based on the results of PRA, risk insight can be provided for risk informed decision-making for NPP.

Dr. Zhao has been engaged in PRA for many years and participate in PRA of high temperature gas cooled reactor nuclear power plant. Besides this, he also participated in the preparation of some nuclear safety regulatory guidelines

Research Status

2019-2023 ,Ministry of Science and Technology of the Peoples Republic of China

Research on risk informed safety margin characteristic analysis technology

Probabilistic  safety margin is the probability that the load of safety index (such as peak  cladding temperature of nuclear fuel rod) exceeds capacity (such as cladding  melting temperature) under a series of possible accident scenarios. The  objective of this project is try to establish the dynamic coupling theory and  method of safety margin characteristic evaluation of Deterministic Safety  Assessment (DSA) and Probabilistic Risk Assessment (PRA). Based on the theory,  the project will study and reveal the nuclear safety characterized by safety  margin, and provide decision-making basis for design, operation and management  of nuclear power plant.

Academic Achievement


Wei Wang, Linggang Zeng, Jun Zhao, Bo Li, Operation Assessment of Service Water Systems under Periodic Inspection and Maintenance, 4th International Conference on System Reliability and Safety, 2019, Rome, Italy.
WeiWang, JiejuanTong, JunZhao*, Application of NUREG/CR-6850 to the fire risk quantification of a High Temperature Gas-Cooled Reactor, Nuclear Engineering and Design, 2018(330): 332-343
Jiejuan TONG*,Jun ZHAO,Tao LIU,Dazhi Xue
Development of Probabilistic Safety Assessment with respect to the first demonstration nuclear power plant of high temperature gas cooled reactor in China, Nuclear Engineering and Design, 2012(251):385-390

Last updated: 2020-10-06