SUN Jun
Associate Professor of Nuclear Science and Engineering
Division Head of Reactor Physics, Thermal Hydraulics, and System Simulation
sunjun@tsinghua.edu.cn
(+86 10) 6278-4826？
Education background
PhD,
Tsinghua University, Power Engineering and Engineering Thermophysics,
2009
B.S.,
Tsinghua University, Thermal Energy and Power Engineering, 2004
Experience
12/2013-present,
Associate Professor, Division of Reactor Physics, Thermal Hydraulics, and System
Simulation, INET
08/2009-11/2013,
Assistant Professor, Division of Reactor Physics, Thermal Hydraulics, and System
Simulation, INET
Social service
Teaching
Training
Lecturer of HTGR technologies (2016- )
Lecturer
of World Nuclear University Tsinghua Week (2017- )
Lecturer
of International Course “Generation IV, Nuclear reactor systems for the future”,
INSTN/CEA, France (2018- )
Lecturer
of PHD4GEN High-Temperature Reactors Summer School, NCBJ, Poland (2020-
)
Co-lecturer of Graduate Course: English Communication and Writing in Nuclear Engineering
Co-lecturer of Graduate Course: Introduction on Nuclear Reactor Engineering
Journal Reviewer
Progress
in Nuclear Energy (Outstanding Reviewer)
Annals
of Nuclear Energy
Physics
of Fluids
Microfluidics
and Nanofluidics
Surface
Science
Heat
Transfer Engineering
Communications
in Nonlinear Science and Numerical Simulations
International
Journal of Metallurgy and Metal Physics
International
Journal of Mechanical Sciences
Service to Professional Associations
Representative
of China, Education and Training Working Group (ETWG), Gen IV International
Forum (GIF) (2016- )
Areas of Research Interests/ Research Projects
Prof.
Sun’s research interests are in the areas of new nuclear reactor designs,
reactor thermal hydraulics, nuclear reactor simulators, and international
cooperation on HTGR.
New
nuclear reactor designs
Designs
of small scale and multi-purpose nuclear reactors, for space electric power
source and space thermal propulsion applications.
Reactor thermal hydraulics
Fundamentals
on flow and heat transfer in gas-cooled reactors, reactor thermal hydraulic
designs and analyses by CFD codes and system codes, code development for reactor
thermal hydraulics.
Nuclear reactor simulators
Code
development and modeling of nuclear reactor simulators, design verifications,
operating procedure verifications, operating analyses by nuclear reactor
simulators.
International cooperation on HTGR
Enhance
and promote international cooperation on HTGR by technical training and joint
researches.
Research Status
2020-2023,
State
Administration of Science, Technology and Industry for National
Defense
Megawatt
Advanced Space Reactor Design and Key Technology Development
Nuclear
reactor technologies based on HTGR could be applied in space explorations by
newly designed concept, including reactor core, fuel, power conversion system
and electric power distribution system. New algorithms and design tools are
necessary. Key technologies need to be validated by experiments and trial
manufacturing of prototypes.
2018-2021,
National
Energy Administration
HTGR
Core Design and System Analyses Self-reliant Code Development and
Validation
Code
development for HTGR 3D reactor neutronics;
Code
development for HTGR thermal hydraulics and accident analyses;
Code
development for HTGR source term analyses;
Verification
and validation of abovementioned new codes.
2018-2021, Ministry
of Science and Techonlogy
China-Indonesia
Joint Laboratory on HTGR
Mainly
targeted on capacity building and joint researches, INET, Tsinghua University,
China collaborates with BATAN, Indonesia to establish the Joint Laboratory on
HTGR and conducts four tasks, including joint studies and development of modular
HTGR technology and its application potentials, joint studies on safety and
licensing of modular HTGR technology, joint development of modular HTGR
simulation technology, and joint studies on localization potentials.
Honors And Awards
HTGR
Physics, Thermal Hydraulics and System Simulation Innovation Team, 2018 China
Nuclear Energy Association Science and Technology Award (Innovation Team), China
Nuclear Energy Association
Academic Achievement
Publications
Jun Sun, Ximing Sun, and Yanhua Zheng*, Transient Study on the HTR-PM with TINTE-vPower Coupling Code Package, Science and Technology of Nuclear Installations, 2020, 5090597.
Yu Ji, Zeguang Li, Jun Sun*, Ersheng You, Minggang Lang, Lei Shi. Numerical Investigation and Parametric Study on Thermal-Hydraulic Characteristics of Particle Bed Reactors for Nuclear Thermal Propulsion, Nuclear Technology, 2020, 206, 1155-1170.
Biao
Zhou, Yu Ji, Jun Sun*, Yuliang Sun. Modified Turbulent Prandtl Number Model for
Helium–Xenon Gas Mixture with Low Prandtl Number, Nuclear Engineering and
Design, 2020, Vol. 366, 110738
Jun
Sun*, Zhe Sui, Chunlin Wei. Applications of HTR-PM Engineering Simulator.
HTR2020, 10th International Conference on High Temperature Reactor, 2020,
Yogyakarta, Indonesia.
Ziping
Liu, Jun Sun*. Preliminary Discussion on the Equivalent Thermal Conductivity
Affected by the Inner Heat Source. ATH’2020: International Topical Meeting on
Advances in Thermal Hydraulics, 2020, France.
Yu Ji,
Ziping Liu, Jun Sun* and Lei Shi. Analysis of the Flow Distribution in a
Particle Bed Reactor for Nuclear Thermal Propulsion. Energies, 2019, 12:
3590.
Yu Ji,
Han Zhang, Jun Sun*, Lei Shi, Thermal Performance Optimization of a Fuel Element
in Particle Bed Reactors for Nuclear Thermal Propulsion, Nuclear Engineering and
Design, 2019, 355, 110316.
Ximing
Sun, Zhipeng Chen, Jun Sun*, Yuan Liu, Yanhua Zheng, Fu Li, Lei Shi. CFD
investigation of bypass flow in HTR-PM. Nuclear Engineering and Design, 2018,
329: 147-155.
Ziping
Liu, Zeguang Li, Jun Sun*, Bypass flow in small absorber sphere channels of the
high-temperature gas-cooled reactor pebble-bed module, Journal of Computational
Multiphase Flows, 2018, 10(3): 128-139.
Ji Yu,
Sun Jun*, Shi Lei, Numerical investigation of convective heat transfer to
supercritical hydrogen in a straight tube, Journal of Nuclear Engineering and
Radiation Science, Transactions of the ASME, 2018, 4, 031012.
Software Copyright
HTGR
Reactor Core Real-time Algorithm, No. 2012SR098790
Reactor
Neutronics Real-time Algorithm, No. 2019SR0531334
HTGR
Thermal Hydraulics and Accident Analyses Program - Talos, No. 2020SR00012042,
2020SR00012044, 2020SR00095792, 2020SR00098007
Nuclear
Thermal Rocket System Analyses Program – PANES, No. 2020SR0585271
Last Updated：2020-10-07
