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个人简介

程杰,男,中共党员,四川仪陇人,工学博士,副教授、硕士生导师。2011年获西安交通大学核工程与核技术学士学位;同年于西安交通大学进入研究生阶段学习,2013年转为博士研究生;2016年至2018年于美国内华达大学拉斯维加斯分校访学;2019年6月获工学博士学位后来校工作。现作为课题负责人主持国家自然科学基金1项(青年),预研课题1项,中央高校项目1项,民品横向项目5项,本科生教改项目1项;作为主要参与人完成各类项目20余项。申请发明专利4项,发表学术论文40余篇(h-index 9),登记软件著作权3项。编写专著1部,译著1部。2022届优秀班主任,2022届毕业设计优秀指导教师。主讲“反应堆热工水力学”、“核动力设备(二)”、“核动力热工水力分析”等专业课程。担任FRONTIERS IN ENERGY RESEARCH期刊评审编辑;Progress in Nuclear Energy、Fusion Energy and Design、International Jounal of Heat and Mass Transfer等杂志审稿人,中国核学会会员,美国核学会会员。 教育经历 2013/09~2019/06 西安交通大学/工学博士/核科学与技术 2011/09~2013/09 西安交通大学 (硕博连读) 2007/09~2011/06 西安交通大学/工学学士/核工程与核技术 工作经历 2023/07~至今 哈尔滨工程大学/核科学与技术学院/核动力装置研究所/副教授 2019/06~2023/06 哈尔滨工程大学/核科学与技术学院/核动力装置研究所/预聘副教授 2016/02~2018/05 内华达大学拉斯维加斯分校/机械工程系/能源研究中心/访问学者

研究领域

反应堆多尺度多物理场耦合方法 聚变堆包层设计与物理/热工/力学分析 核动力装置多目标优化算法开发 新型反应堆概念设计

近期论文

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Kong, Deyan; Liu, Xu; Cheng, Jie*; Wang, Jianjun et al. Method study on failure probability and uncertainty analysis of stress corrosion cracking in fixed parts of PWR. Progress in Nuclear Energy. 162(2023), 104777. 2023. Han, Yifu; Wu, Di*; Cheng, Jie; Wang, Jianjun et al. Optimal design and analysis of lubricating oil system in marine nuclear power based on adaptive genetic algorithm. Progress in Nuclear Energy. 166(2023), 104937. 2023. 严一鸣,郝承明,曲自信,程杰*等. 小型核动力装置抽真空启动过程热力特性及含氧量变化实验研究. 核科学与工程. Vol43,4,952-959. 2023. 孙奥,程杰*,朱东保等. 二次侧非能动余热排出系统启动特性研究. 动力工程学报. Vol43,12,1592-1598. 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

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