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.
