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程杰

Cheng Jie

Department： CNST

Discipline： Nuclear Engineering

Duty：

Prof. Title： Associate Professor

Tutor： Masters' Tutor

Tel： 0451-82569655

Fax： 0451-82569655

E-Mail： jcheng@hrbeu.edu.cn

Postcode： 150001

Add：哈尔滨工程大学31号楼348室

Profile

Cheng Jie, Ph.D, Associate professor, Master's tutor.
Obtained a bachelor's degree in nuclear engineering and nuclear technology from Xi'an Jiaotong University in 2011; entered postgraduate studies at Xi'an Jiaotong University in the same year, and became a doctoral candidate in 2013; visited the University of Nevada, Las Vegas from 2016 to 2018; 2019 In June of that year, he received a doctorate in engineering and then worked at the school.
Currently, as the project leader, he presides over 1 National Natural Science Foundation project (youth), 1 pre-research project, 1 central university project, 5 civilian horizontal projects, and 1 undergraduate education reform project; as a main participant, he has completed 20 projects of various types Remainder.
He has applied for 4 invention patents, published more than 40 academic papers (h-index 9), and registered 3 software copyrights. Compiled 1 monograph and translated 1 book. Excellent class teacher of the class of 2022, and outstanding instructor of the graduation project of the class of 2022.
Lectures on professional courses such as "Reactor Thermal Hydraulics", "Nuclear Power Equipment (2)", "Nuclear Power Thermal Hydraulics Analysis".
He serves as review editor for the journal FRONTIERS IN ENERGY RESEARCH; reviewer for Progress in Nuclear Energy, Fusion Energy and Design, International Journal of Heat and Mass Transfer and other journals; a member of the Chinese Nuclear Society and a member of the American Nuclear Society.

Education

2013/09～2019/06 Xi'an Jiaotong University/Doctor of Engineering/Nuclear Science and Technology

2011/09～2013/09 Xi'an Jiaotong University (Master and Doctorate)

2007/09～2011/06 Xi'an Jiaotong University/Bachelor of Engineering/Nuclear Engineering and Technology

Experience

2023/07~present Harbin Engineering University/School of Nuclear Science and Technology/Nuclear Power Plant Research Institute/Associate Professor

2019/06～2023/06 Harbin Engineering University/School of Nuclear Science and Technology/Nuclear Power Plant Research Institute/Assistant Professor

2016/02～2018/05 University of Nevada, Las Vegas/Department of Mechanical Engineering/Energy Research Center/Visiting Scholar

Research Fields

1) Reactor multi-scale multi-physics coupling method
2) Fusion reactor cladding design and physical/thermal/mechanical analysis
3) Development of multi-objective optimization algorithm for nuclear power plants
4) Concept design of new reactor

Projects

Research on nuclear-thermal-mechanical coupling behavior under fusion reactor envelope breach accident; Project Leader

Three-dimensional reactor core fine analysis technology; Project Leader

Development of intelligent design program for overall layout of nuclear auxiliary plant; Project Leader

Research on the utilization of uranium and plutonium for reprocessing recovery; Project Leader

Research on heat transfer characteristics of heat pipes under ocean conditions; Project Leader

Analysis and experimental research on operating characteristics of vacuum cold start-up; Project Leader

Comprehensive integration optimization technology; Technical Leader

Mechanical evaluation of voltage stabilizer surge tube in Category I and II working conditions; Technical Leader

Passive waste heat removal system simulation calculation service project; technical person in charge

Reactor multidisciplinary optimization system; Technical Leader

Development of comprehensive performance rapid evaluation system for system solution design; Main Participant

Small Modular Reactor of Molten Salt Reactor Design and Testing; Main Participant

Research on thermal hydraulic design and safety analysis and evaluation of the China Fusion Engineering Experimental Reactor (CFETR) cladding; Main Participant

Research on key technologies of supercritical water-cooled cladding; Main Participant

Academic Communication

Gao, Zhibo; Kong, Deyan; Cheng, Jie*; Wang, Jianjun. Research On Surrogate Model Based On Kriging Interpolation. 30th International Conference on Nuclear Engineering. Kyoto, Japan, May 21-26, 2023.

Kong, Deyan; Liu, Xu; Cheng, Jie*; Wang, Jianjun; Zhang, Jinqiang; Chen, Dingyong; Li, Qingzhao; Liu, Yanting. Prediction and Uncertainty Analysis of Stress Corrosion fraction Failure Probability for Pressurized Water Reactor Materials. International Conference on Nuclear Engineering, Proceedings, ICONE, Volume 13, 2022.

Sun, Ao; Cheng, Jie*; Zhu, Dongbao; Tian, Chunping; Li, Pengzheng. INVESTIGATION ON START-UP CHARACTERISTICS OF SECONDARY PASSIVE RESIDUAL HEAT REMOVAL SYSTEM UNDER ROLLING CONDITION. International Conference on Nuclear Engineering, Proceedings, ICONE, Volume 7 -A, 2022.

Li Lingyan, Cheng Jie, Wang Jianjun. Development of thermal hydraulic calculation model of once-through steam generator [C]. The Second Academic Annual Conference of the Nuclear Reactor Thermal Fluid Dynamics Branch of the Chinese Nuclear Society and the 2022 Academic Conference of the China Nuclear Reactor Thermal Hydraulic Technology Key Laboratory Annual meeting and national energy pressurized water reactor technology research and development (experiment).

Che Peng, Wang Jianjun, Cheng Jie, Li Pengzheng. Numerical study of steam jet condensation flow pattern in supercooled water [C]. Proceedings of the Second National Academic Annual Conference on Thermal Fluid Dynamics of Nuclear Reactors, Harbin, 2022.

Liu Xu, Cheng Jie, Wang Jianjun. Failure probability analysis of high and low cycle fatigue fracture of pressurized water reactor structure [C]. The Second Academic Annual Conference of the Nuclear Reactor Thermal Fluid Dynamics Branch of the Chinese Nuclear Society and the China Nuclear Reactor Thermal Hydraulic Technology Key Laboratory 2022 Annual academic meeting and national energy pressurized water reactor technology research and development (experiment).

Cheng Jie, Fan Guangming, Su G.H., Thermal hydraulic parameters optimization of supercritical water cooled solid breeder blanket for CFETR, 5th International Workshop on Heat/Mass Transfer Advances for Energy Conservation and Pollution Control. Novosibirsk, Russia, August 13-16, 2019.

Cheng Jie, Wu Yingwei, Su Guanghui. Thermo-hydraulic analysis of water-cooled blanket based on PWR and SCWR water conditions for CFETR. 24th International Conference on Nuclear Engineering. Charlotte, NC, USA, June 26-30, 2016.

Cheng Jie, Wu Yingwei, Qiu Suizheng, Su Guanghui. Research on neutronics of supercritical water-cooled solid-state experimental envelope. The 14th Reactor Thermal Fluids Conference, Beijing, September 2015.

Cheng Jie, Wu Yingwei, Tian Wenxi, et al., Neutronics design optimization of supercritical-water cooled ceramics blanket for ITER. 8th Joint International Symposium on Nuclear Science and Technology, XJTU-UT-SJTU Joint Workshop, Ibaraki, Japan, June 26 -29, 2015.

Admissions

Recruiting master's degree students in the research direction of reactor physics and thermal engineering coupling & reactor optimization design

Course For Undergraduate

Lecture on "Nuclear Power Equipment II";

Lecture on "Reactor Thermal Hydraulics";

Teaching Assistant of "Two Phase Flow";

Course For Postgraduate

Lecture on "Nuclear Power Thermal Hydraulic Analysis";

Teaching assistant for "Numerical Analysis of Flow Heat Transfer";

Practical Teaching

Nuclear power plant course design (1);

Nuclear power plant course design (3);

Teaching Research

Social Position

Patent

Book

Article

Zeng, Xiaobo; Wang, Meng; Fan, Guangming; Cheng, Jie*; Yan, Changqi. Experimental study on the flow behaviors in a vane-type separator. Chemical Engineering and Processing – Process Intensification. 2023, 186, 109328.
Sun, Ao; Cheng, Jie*; Yan, Changqi; Zhu, Dongbao; Tian, Chuanping; Li, Pengzheng. Experimental study on condensation heat transfer characteristics in C-shaped tube under rolling conditions. Nuclear Engineering and Design. 2023, 408, 112327.
Sun, Ao; Cheng, Jie*; Yan, Changqi; Zhu, Dongbao; Tian, Chuanping; Li, Pengzheng. Experimental study on the influence of inclination on operating characteristics of secondary side passive residual heat removal system. Annals of Nuclear Energy. 2023, 191, 109922.
Zeng, Xiaobo; Wang, Meng; Fan, Guangming; Cheng, Jie*; Yan, Changqi. A theoretical model for calculating particle trajectory in a vane-type separator. Chemical Engineering Research and Design, 2023, 194, 529-541.
Zhang, Rui; Du, Zhiyuan; Ren, Tingting; Shi, Jiangwu; Cheng, Jie*. Development of flow boiling mechanism model and its application to rectangular narrow channel under atmosphere pressure, Progress in Nuclear Energy, 2022,152:104381.
Cheng, Jie; Wang, Zhenying*; Lu, Chuan; Zhang, Jibin; Bi, Shumao; Feng, Qilong; Control Rod Drop Hydrodynamic Analysis Based on Numerical Simulation, Frontiers in Energy Research, 2020, 8: 0-342.
Li, Xinyu; Cheng, Jie*; Zhang, Dalin; Dai, Zhiwen; Design and optimization of passive residual heat removal system for lead-bismuth reactor SVBR-100, International Journal of Energy Research, 08 November 2020.
Cheng Jie, Wu Yingwei, Tian Wenxi, et al. Neutronics and thermo-hydraulic design of supercritical-water cooled solid breeder TBM. Fusion Engineering and Design, Vol. 92, 52-58, 2015.
程杰, 巫英伟, 田文喜, 等, 超临界水冷固态实验包层中子学与热工水力特性研究, 原子能科学技术, 49, 1966-1972, 2015.
Cheng Jie, Wu Yingwei, Tian Wenxi, et al., Neutronics design optimization of supercritical-water cooled ceramics blanket for ITER. 8th Joint International Symposium on Nuclear Science and Technology, XJTU-UT-SJTU Joint Workshop, Ibaraki, Japan, June 26-29, 2015.
程杰, 巫英伟, 秋穗正, 苏光辉. 超临界水冷固态实验包层中子学研究. 第14届反应堆热工流体会议, 北京, 2015年9月.
Cheng Jie, Wu Yingwei, Cui Shijie, et al., Conceptual design and coupled neutronic/thermal-hydraulic/mechanical research of the supercritical water cooled ceramic blanket for CFETR. Fusion Engineering and Design, Vol. 138, 272-281, 2019.
Cheng Jie, Wu Yingwei, Su G.H, et al., Neutronic and thermo-hydraulic analyses of water-cooled blanket based on pressurized/supercritical water conditions for CFETR. Journal of Nuclear Engineering and Radiation Science, Vol. 5(4),2019
Cui Shijie, Zhang Dalin, Cheng Jie, et al., Thermo-hydraulic analysis of two Chinese Helium-Cooled Ceramic Breeder TBM designs. The Seventh China–Korea Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-7). Kunming, China, October 14-17, 2015.
Cheng Jie, Wu Yingwei, Su Guanghui. Thermo-hydraulic analysis of water-cooled blanket based on PWR and SCWR water conditions for CFETR. 24th International Conference on Nuclear Engineering. Charlotte, NC, USA, June 26-30, 2016.
Cui Shijie, Zhang Dalin, Cheng Jie, et al., Thermo-hydraulic analysis of the optimized helium cooled solid breeder blanket for CFETR. 24th International Conference on Nuclear Engineering. Charlotte, NC, USA, June 26-30, 2016.
Cui Shijie, Zhang Dalin, Cheng Jie, et al., Theoretical research on the coupled neutronic/thermal-hydraulic/mechanical characteristics of the optimized helium cooled solid breeder blanket for CFETR. The 5th International Conference on Nuclear and Renewable Energy Resources (NURER2016) Hefei, Anhui, China, 18-21 Sep. 2016
Cui Shijie, Zhang Dalin, Cheng Jie, et al., Numerical research on the neutronic/thermal-hydraulic/mechanical coupling characteristics of the optimized helium cooled solid breeder blanket for CFETR. Fusion Engineering and Design, Vol. 114, 141-156, 2017.
Zhang Dalin, Cui Shijie, Cheng Jie et al., Thermal and Mechanical Analyses of the CLAM Steel in Supercritical-water Cooled Ceramic Breeder Blanket for CFETR. International Workshop on Mechanics of Energy Materials (IWMEM 2017), The University of Sydney, Australia, 8-11 Nov 2017.
Cui Shijie, Zhang Dalin, Ge Jian, Cheng Jie, et al., Development and application of a neutronics/thermal-hydraulics coupling optimization code for the CFETR helium cooled solid breeder blanket with mixed pebble beds. Fusion Engineering and Design, Vol. 125, 24-37, 2017.
Cui Shijie, Zhang Dalin, Lian Qiang, Cheng Jie, et al., Evaluation and optimization of tritium breeding, shielding and nuclear heating performances of the helium cooled solid breeder blanket for CFETR. International Journal of Hydrogen Energy, Vol. 42, 24263-24277, 2017.
Cui Shijie, Zhang Dalin, Lian Qiang, Tian Wenxi, Cheng Jie, et al., Development of a neutronics/thermal-hydraulic coupling optimization code and its application on the CFETR HCSB blanket. Fusion Engineering and Design, Vol. 122, 139-152, 2017.
Chu Wenxiao, Bennett Katrine, Cheng Jie, et al., A review of using supercritical CO2 Brayton cycle in renewable energy application. Journal of Renewable Energy and Sustainable Development, 4(1): 14-20, 2018.
Wei Hongyang, Chen Yi-Tung, Lan Kuan-Che, Cheng Jie, Parametric study of thermal molten salt reactor neutronics criticality behavior. Progress in Nuclear Energy, 108: 409-418, 2018.
Chen Yi-Tung, Chu Wen-Xiao, Bennett Katrine, Cheng Jie, Wang Qiu-Wang, Numerical study on supercritical CO2 in PCHE with asymmetrical airfoil fins. 16th International Heat Transfer Conference (IHTC16), Beijing, China, 10-15 Aug 2018.
Zhang Dalin, Cui Shijie, Cheng Jie et al., Improving the optimization algorithm of NTCOC for application in the HCSB blanket for CFETR Phase II. Fusion Engineering and Design, Vol. 135, 216-227, 2018.
Chu Wenxiao, Bennett Katrine, Cheng Jie, et al., Numerical study on a novel hyperbolic inlet header in straight-channel printed circuit heat exchanger. Applied Thermal Engineering, 146:805-814, 2019.
Chu Wenxiao, Bennett Katrine, Cheng Jie, et al., Thermo-hydraulic performance of printed circuit heat exchanger with different cambered airfoil fins. Heat Transfer Engineering, 41(8), 2019.

Updated by Sep. 2023
For detail, Visit: https://www.researchgate.net/profile/Jie-Cheng-15

Honors

Awards

Personal Information

Introduction：
Education Background :
Professional Experience :
Qualifications and Skills :
Academic Positions and Titles :

Research

Research Fields：
Projects：
Honors and Awards、Academic Activities：

Teaching

Admission:
Courses:
Practical Teaching：

Publications

Books:
Journal and Conferences:
Patents:
Software Copyrights:	"

English

Contact:
Email: jie.cheng@foxmail.com
jcheng@hrbeu.edu.cn
Tel: +86-18904508971
Fax: +86-451-82569655
Add: Room 211, Sanjia Building, 145 Nantong St., Harbin, Heilongjiang, China. 150001

Education:

PhD, 2019, Xi'an Jiaotong University, Nuclear Engineering
BS, 2011, Xi'an Jiaotong University, Nuclear Engineering

Occupation:

Associate Professor, 2023-recent, Harbin Engineering University, College of Nuclear Science and Technology
Assistant Professor, 2019-2023, Harbin Engineering University, College of Nuclear Science and Technology
Visiting scholar, 2016-2018, University of Nevada, Las Vegas, Mechanical engineering (Center for energy research)

Research:

Reactor multi-scale and multi-physics coupling method;
Fusion reactor blanket design and physical/thermal/mechanical analysis;
Development of multi-objective optimization algorithm for nuclear power plant;
Conceptual Design of Advanced Reactor System.

For more research information, visit https://www.researchgate.net/profile/Jie-Cheng-15

程杰