PhD, Tsinghua University, Nuclear Science and Engineering, 2006
B.E., Xi’an 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
Reliability Engineering and Risk Analysis
Areas of Research Interests/ Research Projects
Dr Zhao’s 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
2019-2023 ,Ministry of Science and Technology of the People’s 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.
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