近期论文
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期刊论文
1. H. Cheng, J. Zhao*, M.K. Rowinski, Study on two wall temperature peaks of supercritical fluid mixed convective heat transfer in circular tubes. International Journal of Heat and Mass Transfer, 113: 257-267, 2017. （JCR Q1中科院大类二区，Top）
2. H. Cheng, J. Zhao*, J. Wang, Experimental investigation on the characteristics of melt jet breakup in water: The importance of surface tension and Rayleigh-Plateau instability. International Journal of Heat and Mass Transfer, 132: 388-393, 2019. （JCR Q1中科院大类二区，Top）
3. H. Cheng, A.B. Yanlin, J. Wang, J. Zhao*, Diameter effect on the wall temperature behaviors during supercritical water heat transfer deterioration in circular tubes and annular channels. Frontiers in energy research, 7, 73, 2019. （JCR Q3中科院大类四区）
4. H. Cheng, S. Cheng*, J. Zhao*, Study on corium jet breakup and fragmentation in sodium with a GPU-accelerated color-gradient lattice Boltzmann solver, International Journal of Multiphase Flow, 126, 103264, 2020. （JCR Q2中科院大类二区）
5. H. Cheng, X. Chen, Y. Ye, S. Cheng*, Systematic experimental investigation on the characteristics of molten lead-bismuth eutectic fragmentation in water, Nuclear Engineering and Design, 371, 110943, 2021. （JCR Q2中科院大类三区）
6. S. Cheng*, Y. Zou, Y. Dong, H. Cheng, Y. Ye, X. Chen, Y. Chen, Experimental study on pressurization characteristics of a water droplet entrapped in molten LBE pool, Nuclear Engineering and Design, 378, 111192, 2021. （JCR Q2中科院大类三区）
7. H. Cheng, J. Zhao*, S. Saito, S. Cheng*, Study on melt jet breakup behavior with nonorthogonal central-moment MRT color-gradient lattice Boltzmann method, Progress in Nuclear Energy, 136, 103725, 2021. （JCR Q1中科院大类三区）
8. H. Cheng, Z. Mai, X. Zhu, L. Wang*, J. Wang*, An innovation idea for SBLOCA mitigation strategy: Self-coagulation system in comparison with human hemostatic mechanism, Progress in Nuclear Energy, 138, 103832, 2021. （JCR Q1中科院大类三区）
9. R. Xu, S. Cheng*, S. Li, H. Cheng, Knowledge from recent investigations on sloshing motion in a liquid pool with solid particles for severe accident analyses of sodium-cooled fast reactor, Nuclear Engineering and Technology, 54(2): 589-600, 2022. （JCR Q2中科院大类三区）
10. H. Cheng, Z. Mai, Y. Li, S. Cheng*, Fundamental experiment study on the fragmentation characteristics of molten lead jet direct contact with water, Nuclear Engineering and Design, 386, 111560, 2022. （JCR Q2中科院大类三区）
11. L. Wang, W. Ye, X. He, S. Wu, P. Ming, J. Wang, H. Cheng*, B. Yan*, Experimental study on the CHF enhancement effect of nanofluids on the oxidized low carbon steel surface, Applied Thermal Engineering, 204, 117968, 2022. （JCR Q1中科院大类二区，top）
12. H. Cheng, S. Cheng*, J. Wang*, Numerical study on the effect of jet cross section shape on the corium jet breakup behavior with lattice Boltzmann method, Frontiers in Energy Research, 10, 834237, 2022. （JCR Q3中科院大类四区）
13. Y. Xu, R. Xu, H. Cheng*, X. Liu*, S. Cheng, Numerical simulation of jet breakup phenomenon during severe accident of sodium-cooled fast reactor using MPS method, Annals of Nuclear Energy, 172, 109087, 2022. （JCR Q2中科院大类三区）
14. Z. Mai, Z. Zhao, H. Cheng*, S. Cheng*, J. Zhao, Numerical study on the release and migration behavior of fission gas in molten LBE Pool, Frontiers in Energy Research, 10, 964841, 2022. （JCR Q3中科院大类四区）
15. S. Tan, Y. Zhong, H. Cheng*, S. Cheng*, Experimental investigation on the characteristics of molten lead-bismuth non-eutectic alloy fragmentation in water, Nuclear Science and Techniques, 33(9), 115, 2022. （JCR Q2中科院大类一区）
16. H. Cheng, S. Tan, S. Cheng, Study on the effect of jet cross section shape on molten fuel fragmentation behavior with simulant experiments, Nuclear Engineering and Design, 400, 112077, 2022. (JCR Q2中科院大类三区)
17. K. Wang, H. Cheng, X. Liu, C.-Y. Li, K. Okamoto, How nucleation site density affects the nucleate boiling crisis: Explanations of varied experimental results based on a bubble percolation method, International Communications in Heat and Mass Transfer, 140, 106552, 2023. （JCR Q1中科院大类二区，top）
18. S. Tan, S. Cheng, K. Wang, X. Liu, H. Cheng*, Jun Wang*, The development of Micro and Small Modular Reactor in the future energy market, Frontiers in Energy Research, 11, 1149127, 2023. （JCR Q3中科院大类四区）
19. Z. Deng, S. Cheng*, H. Cheng, Experimental investigation on pressure-buildup characteristics of a water lump immerged in a molten lead pool, Nuclear Science and Techniques, 34(3), 35, 2023 (JCR Q2中科院大类一区)
20. 陈松徽, 程辉, 成松柏. SGTR事故工况下射流行为模拟实验研究[J]. 工程热物理学报, 2023, 44.
21. H. Cheng, S. Chen, H. Huang, S. Cheng*, Z. Zhao*, J. Zhao, Study on water jet penetration behavior in molten LBE during SGTR accident with simulant experiments, Nuclear Engineering and Design, 411, 112413, 2023. (JCR Q2中科院大类三区)
22. K. Lau, S. Khan, D. Ji, C. Eze, H. Cheng, J. Zhao, Empirical modelling of supercritical Nusselt number correlations with possible combinations of indicative dimensionless variables, International Communications in Heat and Mass Transfer, 148, 107038, 2023. （JCR Q1中科院大类二区，top）
23. J. Zhu, Y. Lin, H. Cheng, S. Tan, X. Li, J. Wen, R. Tian, Numerical simulation of ultrasonic velocity in wet steam, Nuclear Engineering and Design, 414, 112578, 2023. (JCR Q2中科院大类三区)
24. M. Moustafa, T. Ruifeng, J. Wen, W. Bo, A. Ullah, H. Mohamad, H. Cheng, Modeling of wavy water film by application of artificial neural network - a state of art study, Nuclear Engineering and Design, 417, 112731, 2024. (JCR Q2中科院大类三区)
25. S. Chen, S. Cheng*, H. Cheng*, Study of bubble migration characteristics in downward flow under SGTR accidents of LFR with similarity experiments , Annals of Nuclear Energy, 199, 110363,2024.（JCR Q2中科院大类三区）
26. S. Tan, S. Xia, H. Cheng *, S. Cheng*, Numerical simulation of in-vessel steam explosion for China third-generation PWR, 424, 113258, 2024. (JCR Q2中科院大类三区)
会议论文
1. H. Cheng*, H. Li, J. Yin, X. Gu, Y. Hu, D. Wang, Investigation of the distortion suction flow on the performance of the canned nuclear coolant pump, 6th International Symposium on Fluid Machinery and Fluid Engineering (ISFMFE 2014), Wuhan, China, October 22-25, 2014.
2. J. Yin, J. Li, H. Cheng, Y. Hu, D. Wang, Investigation on the Backflow Induced Pre-Rotation of RCP, Proceedings of the 22th International Conference on Nuclear Engineering (ICONE22), Prague, Czech, July 7-11, 2014.
3. H. Cheng*, J. Zhao, Large-eddy simulation of thermal fatigue in a supercritical water mixing tee, International seminar on Subchannel Analysis, CFD, and CHF (ISACC-2015), Shenzhen, China, December 06-08, 2015.
4. J. Zhao, H. Cheng, M.K. Rowinski, Investigations on the Fundamental Transport Phenomena of Supercritical Fluids Applications in Nuclear Energy Systems, 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, California, USA, April 17-20, 2016.
5. H. Cheng*, J. Zhao, Numerical Investigation on Heat Transfer of Supercritical Water in Rod Bundle Under Suddenly Decreased Mass Flux Condition, Proceedings of the 24th International Conference on Nuclear Engineering (ICONE24), Charlotte, NC, United States, June 26-30, 2016
6. H. Cheng*, J. Zhao, Mitigation of heat transfer deterioration in supercritical water using vortex generator, 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017), Fukui and Kyoto, Japan, April 24-28, 2017.
7. H. Cheng*, J. Zhao, Numerical investigation of melt jet breakup with different shapes in water pool, Proceedings of the 25th International Conference on Nuclear Engineering (ICONE25), Shanghai, China, July 2-6, 2017.
8. K.W. Wong, H. Cheng, J. Zhao, Numerical Study on Mitigation of Heat Transfer Deterioration in Supercritical CO2 Heat Exchanger Application, Proceedings of the 25th International Conference on Nuclear Engineering (ICONE25), Shanghai, China, July 2-6, 2017.
9. H. Cheng*, J. Zhao, Numerical and Experimental Investigation of Melt Jet Breakup in A Water Pool, ANS Best Estimate Plus Uncertainty International Conference (BEPU 2018), Real Collegio, Lucca, Italy, May 13-19, 2018.
10. C. Eze, H. Cheng, J. Zhao, Investigation on Supercritical Fluids Heat Transfer Deterioration and Its Mitigations, 16th International Heat Transfer Conference (IHTC16), Beijing, China, August 10-15, 2018.
11. H. Cheng*, J. Zhao, Investigation on the characteristics of melt jet breakup in water with both experiment and LBM methods, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019), Portland, OR, United States, August 18-23, 2019.
12. R. Xu, S. Cheng, H. Cheng, Progress of recent studies on sloshing motion in a liquid pool with solid particles, 2020 International Topical Meeting on Advances in Thermal Hydraulics (ATH'2020), Paris-Saclay, France, June 12-16, 2022.
13. Z. Mai, Z. Zhao, H. Cheng*, S. Cheng, Three-dimensional numerical simulation of the release and migration behavior of fission gas bubbles in advanced reactor pool under serious accident, Proceedings of the 29th International Conference on Nuclear Engineering (ICONE29), Shenzhen, China, August 8-12, 2022
14. S. Tan, H. Cheng*, S. Cheng, Experimental Investigation on the Effect of Jet Cross Section Shape on Fragmentation Characteristics of Molten Fuel Using Simulant Materials, The 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 13), Hsinchu, Taiwan, China, September 5-10, 2022.
15. 陈松徽，程辉，成松柏，水在熔融铅铋共晶合金中射流行为的模拟实验研究，2023年核反应堆系统设计技术重点实验学术年会，四川成都，2023年2月28日-3月2日
16. 曹勤创，程辉，成松柏，熔融铅铋共晶合金中气泡上升行为的实验研究，2023年核反应堆系统设计技术重点实验学术年会，四川成都，2023年2月28日-3月2日
17. 谭少杰，程辉，成松柏，射流形状对熔融燃料碎裂行为影响的模拟实验研究，2023年核反应堆系统设计技术重点实验学术年会，四川成都，2023年2月28日-3月2日
18. 谭少杰， 成松柏， 程辉，严重事故下射流碎化行为的模拟实验研究，国家能源核电软件重点实验室2022-2023 年学术交流会暨学术年会，2023年6 月6-8 日
19. 陈松徽， 成松柏， 程辉， 刘晓星，流动液体中气泡迁移行为实验研究，国家能源核电软件重点实验室2022-2023 年学术交流会暨学术年会，2023年6 月6-8 日
20. 曹竞翔， 程辉， 成松柏，熔融 LBE 池中气体卷吸行为的模拟实验研究，国家能源核电软件重点实验室2022-2023 年学术交流会暨学术年会，2023年6 月6-8 日
21. S. Tan, H. Cheng*, S. Cheng, Study on the Corium Jet Breakup Behavior with Different Simulant Materials under Different Conditions, the 10th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-10), Jeju, Korea, Nov. 25-29, 2023.
22. 谭欣，李嘉元，翁子豪，程辉，LBM在第四代核能系统研究中的应用综述，2024 年度核反应堆技术全国重点实验室学术年会，四川成都，2024年4月16日-4月20日
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