Cai Jiejin, PhD, Professor
Address:School of Electric Power,South China University of Technology, 381 Road Wushan, Tianhe, Guangzhou 510640 China
Tel: +86-134-5049-1876
Fax: +86-20-8711-0164
E-mail :epjjcai@scut.edu.cn
Research Interests
1. Nuclear Reactor Thermo hydraulics and Safety
2. Two-phase Flow and Heat Transfer
3. Supercritical Water Cooled Reactor
4. Computational Fluid Dynamics
5. Artificial Intelligence Technology
Academic Experience
1. Professor in School of Electric Power，South China University of Technology, China(2015 – Present)
2. Professor / Associate Professor / Assistant dean in Sino-French Institute of Nuclear Engineering & Technology，Sun Yat-Sen University, China(2011 – 2015)
3. Researcher in Thermo hydraulic Safety Research Group, Reactor Safety Research Unit, Nuclear Safety Research Center, Japan Atomic Energy Agency, Japan(2009 – 2011)
4. Researcher in Department of Nuclear Engineering and Management, The University of Tokyo, Japan(2007 – 2009)
Education:
Ph.DSouth China University of Technology, China, 2007
M.S.South China University of Technology, China, 2004
B.S.Southwest Jiaotong University, Chian, 1999
Professional Activities:
Editorial Board of World Journal of Nuclear Science and Technology
Council of Fluid Mechanics and Engineering in the Guangdong Society of Theoretical and Applied Mechanics
Peer reviewer of the international journals:
1. Energy
2. Nuclear Engineering and Design
3. Annals of Nuclear Energy
4. Progress of Nuclear Energy
5. Applied Thermal Engineering
6. Engineering Optimization
7. IET Generation, Transmission & Distribution
8. European Transactions on Electrical Power
9. Mathematics and Computers in Simulation
10. IEEE Transactions on Industrial Electronics
11. International Journal of Electrical Power and Energy Systems
12. Engineering Applications of Computational Fluid Mechanics
13. International Journal of Heat and Mass Transfer
14. Energy Conversion and Management
15. International Journal of Heat and Mass Transfer
16. Chemical Engineering Research and Design
17. International Journal of Thermal Sciences
Peer reviewer of the funding projects:
1. National Natural Science Foundation of China
2. Guangdong’s Natural Science Foundation of China
3. Jiangsu’s Natural Science Foundation of China
Publications
Selected Refereed Journals
1.Ye Wang, Jiejin Cai*, Qiong Li*, Numerical simulation of large bubble rising behavior using diffuse interface method, International Journal of Hydrogen Energy, May 2017. (Accepted)
2.Ye Wang, Jiejin Cai*, Numerical investigation on bubble evolution during nucleate boiling using diffuse interface method, International Journal of Heat and Mass Transfer, 112: 28-38, September 2017.
3.Jiejin Cai*, Byeongnam Jo, Nejdet Erkan, Koji Okamoto, Effect of non-condensable gas on thermal stratification and flow patterns in suppression pool, Nuclear Engineering and Design, 300: 117-126, April 2016.
4.Shuanshuan Guo, Jiejin Cai*, Huiyong Zhang, Huaqiang Yin, Xingtuan Yang, Study of the Distribution of Steam Plumes in the PANDA Facility Using CFD Code, Nuclear Engineering and Design, 289: 81-91, August 2015.
5.Qingyun Zeng, Jiejin Cai*, Huaqiang Yin, Xingtuan Yang, Tadashi Watanabe, Numerical simulation of single bubble condensation in subcooled flow using OpenFOAM, Progress in Nuclear Energy, 83: 336-346, August 2015.
6.Weifeng Xu, Jiejin Cai*, Shichang Liu, Qi Tang, Analysis of the Influences of Thermal Correlations on Neutronic-Thermohydraulic Coupling Calculation of SCWR, Nuclear Engineering and Design, 284: 50-59, April 2015.
7.Jiejin Cai*, Claude Renault, Junli Gou, Supercritical water-cooled reactors, Science and Technology of Nuclear Installations, 2014: 1-2, August 2014.
8. Qingyun Zeng, Jiejin Cai*, Three-dimension simulation of bubble behavior under nonlinear oscillation, Annals of Nuclear Energy, 63: 680-690, January 2014.
9. Shichang Liu, Jiejin Cai*, Design & optimization of two breeding thorium-uranium mixed SCWR fuel assemblies, Progress of Nuclear Energy, 70(2014): 6-19 January 2014.
10. Shichang Liu, Jiejin Cai*, Convergence Analysis of Neutronic/Thermohydraulic Coupling Behavior of SCWR, Nuclear Engineering and Design, 265: 53-62, December 2013.
11. Qi Tang, Jiejin Cai*, Various startup system designs of HPLWR and their thermal analysis, Nuclear Engineering and Design, 265: 791-800, December 2013.
12. Shichang Liu, Jiejin Cai*, Neutronic and thermohydraulic characteristics of a new breeding thorium-uranium mixed SCWR fuel assembly, Annals of Nuclear Energy, 62(1): 429-436, December 2013.
13. Li Guo, Wenjian Liu, Jiejin Cai*, Bowen Hong, Chengshan Wang, A two-stage optimal planning and design method for combined cooling, heat and power microgrid system, Energy Conversion and Management, 74(1): 433-445, October 2013.
14. Shichang Liu, Jiejin Cai*, Neutronics Assessment of Thorium-based Fuel Assembly in SCWR, Nuclear Engineering and Design, 260(1): 1-10, July 2013.
15. Shichang Liu, Jiejin Cai*, Studies of fuel loading pattern optimization for a typical pressurized water reactor (PWR) using improved pivot particle swarm method, Annals of Nuclear Energy, 50(1): 117-125, December 2012.
16. Jiejin Cai*, Applying support vector machine to predict the critical heat flux in concentric-tube open thermosiphon, Annals of Nuclear Energy, 42(1):114-122, May 2012.
17. Jiejin Cai*, Tadashi Watanabe, Numerical simulation of thermal stratification in cold legs by using OpenFOAM, Progress in Nuclear Science and Technology, 2(1):107-113, October 2011.
18. Jiejin Cai*, Yuki Ishiwatari, Satoshi Ikejiri, Yoshiaki Oka, Thermal and Stability Considerations for a Supercritical Water-Cooled Fast Reactor with downward-flow channels during Power-Raising Phase of Plant Startup, Nuclear Engineering and Design, 239(4):665-679, April 2009.
Patents
19. Jiejin Cai, Xixiang Zeng, An intelligent measure device of critical heat flux, 2012. ( Utility model, No. ZL201120517741.9)
20. Jiejin Cai, Qi Tang, A measure and alarm device of DNBR of PWR reactors, 2012. ( Invention patent, No. ZL201210573963.1)
21. Jiejin Cai, Shichang Liu, A calculation method of coupling neutronic and thermalhydraulics calculation of nuclear reactors, 2012. ( Invention patent, No. ZL201210575574.2)
22. Jiejin Cai, Zhixiong Tan, An online measure and alarm device of fuel damage in nuclear reactors, 2012. ( Utility model, No. ZL201620228378.1)
23. Jiejin Cai, Zhixiong Tan, An online measure and alarm device of fuel damage in nuclear reactors, 2012. ( Invention patent, No. ZL201610169633.4)
Software:
24. Jiejin Cai, Shichang Liu, Qi Tang, Advanced Reactor Neutronics-Thermohydraulics Coupling Calculation Code [Shorted as: ARNT] V1.0, 2013. (No. 2013SR117088)
Honors and Awards:
1.Most Cited Annals of Nuclear Energy Articles (The most cited articles published since 2011)，2016.
2.Most Cited International Journal of Electrical Power & Energy Systems (The most cited articles published since 2010)，2015.
3.JSPS Fellowship Award，2015.
4. 2013 Award for Excellence in Reviewing, Annals of Nuclear Energy, Elsevier 2014.
5. Shichang Liu, Jiejin Cai, Design analysis of a breeding uranium-thorium mixed fuel assembly in SCWR, Third-grade of the Best Paper Award in Annual Meeting of Chinese Nuclear Society, 2013.
6. Shichang Liu, Jiejin Cai, Study on neutronic characteristics and neutronic-thermohydraulic coupling behavior of SCWR with thorium-based fuel, Proceedings of the 21th International Conference on Nuclear Engineering (ICONE21) July 29-Agust 2, 2013, Chengdu, China. (Qian Sanqiang Award for the ICONE 21 Student Best Paper Competition).
7. Awards for the valuable contribution as Panelist at ICONE21, July 29-Agust 2, 2013, Chengdu, China.
8. The Seventh Talents of “Thousand-Hundred-Ten Engineering” for the Universities in Guangdong Province 2012.
9. Program for New Century Excellent Talents in University, Ministry of Education, 2011.
10. Award of Excellent Thesis of PhD, SCUT, 2009.
Selected Sponsored Research Projects:
1. National Natural Science Foundation of China Funding Project, “Research on neutronic and thermohydraulic characteristics of PWR core loaded accident tolerant fuel”, 2017-2020 (PI);
2. China Nuclear Power Technology Research Institute Funding Project, “Development and validation of reactor design software”, 2017-2019 (PI);
3. Fundamental Research Funds for the Central Universities, “Research on flow and heat transfer in passive residual heat removal system for nuclear reactors”, 2017-2019 (PI).
4. China Nuclear Power Technology Research Institute Funding Project, “Schematic design of ultra-safe water-cooled reactor”, 2016-2017 (PI);
5. Guangdong Provincial Science and Technology Funding Project, “Research & Development of diagnostic system of nuclear fuel damage and its application”, 2016-2017 (PI);
6. Japan Society for the Promotion of Science Funding Project, “Research on direct contact condensation and thermal stratification in BWR torus type suppression pool”, 2015-2015 (PI);
7. Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Funding Project, “Numerical research on interface behavior of gas-liquid two-phase flow under earthquake condition”, 2015-2016 (PI);
8. China Nuclear Power Technology Research Institute Funding Project, “Validation & Verification of Reactor Thermal Hydraulic and Design Codes”, 2014-2016 (PI);
9. China Nuclear Power Technology Research Institute Funding Project, “Investigation on the nuclear engineering laboratories”, 2014-2015 (PI);
10. Tianjin University Funding Project, “Modeling and Optimization of Combined Cooling, Heat, and Power Microgrid System”, 2013-2014 (PI);
11. Ministry of Education Funding Project, “Program for New Century Excellent Talents in University”, 2011-2013 (PI);
12. Fundamental Research Funds for the Central Universities, “Research on Critical Heat Flux Characteristics”, 2011-2013 (PI).
Teaching Record
For undergraduate students:
1. Nuclear Reactor Safety,
2. Nuclear Reactor Operation,
3. Principle of Nuclear Engineering,
4. Introduction to the Application of Nuclear Technology,
5. Nuclear Reactor Thermal-hydraulics,
6. Heat Transfer,
7. Thermal Machine,
8. Principles and Design of Nuclear Reactors,
For graduate students:
9. Advanced Nuclear Reactor Engineering,
10. Numerical Simulation of Flow and Heat Transfer.