| Study on two wall temperature peaks of supercritical fluid mixed convective heat transfer in circular tubes H Cheng, J Zhao, MK Rowinski International journal of heat and mass transfer 113, 257-267, 2017 | 52 | 2017 |
| Experimental investigation on the characteristics of melt jet breakup in water: The importance of surface tension and Rayleigh-Plateau instability H Cheng, J Zhao, J Wang International Journal of Heat and Mass Transfer 132, 388-393, 2019 | 27 | 2019 |
| Investigation of the distortion suction flow on the performance of the canned nuclear coolant pump H Cheng, H Li, J Yin, X Gu, Y Hu, D Wang 2014 ISFMFE - 6th International Symposium on Fluid Machinery and Fluid …, 2014 | 21 | 2014 |
| Numerical simulation of jet breakup phenomenon during severe accident of sodium-cooled fast reactor using MPS method Y Xu, R Xu, H Cheng, X Liu, S Cheng Annals of Nuclear Energy 172, 109087, 2022 | 9 | 2022 |
| Experimental study on the CHF enhancement effect of nanofluids on the oxidized low carbon steel surface L Wang, W Ye, X He, S Wu, P Ming, J Wang, H Cheng, B Yan Applied Thermal Engineering 204, 117968, 2022 | 9 | 2022 |
| Study on corium jet breakup and fragmentation in sodium with a GPU-accelerated color-gradient lattice Boltzmann solver H Cheng, S Cheng, J Zhao International Journal of Multiphase Flow, 103264, 2020 | 8 | 2020 |
| Knowledge from recent investigations on sloshing motion in a liquid pool with solid particles for severe accident analyses of sodium-cooled fast reactor R Xu, S Cheng, S Li, H Cheng Nuclear Engineering and Technology, 2022 | 6 | 2022 |
| Experimental study on pressurization characteristics of a water droplet entrapped in molten LBE pool S Cheng, Y Zou, Y Dong, H Cheng, Y Ye, X Chen, Y Chen Nuclear Engineering and Design 378, 111192, 2021 | 6 | 2021 |
| Study on melt jet breakup behavior with nonorthogonal central-moment MRT color-gradient lattice Boltzmann method H Cheng, J Zhao, S Saito, S Cheng Progress in Nuclear Energy 136, 103725, 2021 | 6 | 2021 |
| Fundamental experiment study on the fragmentation characteristics of molten lead jet direct contact with water H Cheng, Z Mai, Y Li, S Cheng Nuclear Engineering and Design 386, 111560, 2022 | 5 | 2022 |
| Systematic experimental investigation on the characteristics of molten lead-bismuth eutectic fragmentation in water H Cheng, X Chen, Y Ye, S Cheng Nuclear Engineering and Design, 110943, 2021 | 5 | 2021 |
| Diameter effect on the wall temperature behaviors during supercritical water heat transfer deterioration in circular tubes and annular channels H Cheng, AB Yanlin, J Wang, J Zhao Frontiers in energy research 7 (73), 2019 | 5 | 2019 |
| Characteristics of pressure fluctuation between rotor and stator of canned nuclear coolant pump Z Yue, Z Jige, Y Junlian, C Hui, W Dezhong Atomic Energy Science and Technology 48, 2014 | 4 | 2014 |
| Study on water jet penetration behavior in molten LBE during SGTR accident with simulant experiments H Cheng, S Chen, H Huang, S Cheng, Z Zhao, J Zhao Nuclear Engineering and Design 411, 112413, 2023 | 2 | 2023 |
| Experimental investigation on pressure-buildup characteristics of a water lump immerged in a molten lead pool ZJ Deng, SB Cheng, H Cheng Nuclear Science and Techniques 34 (3), 35, 2023 | 2 | 2023 |
| How nucleation site density affects the nucleate boiling crisis: Explanations of varied experimental results based on a bubble percolation method K Wang, H Cheng, X Liu, CY Li, K Okamoto International Communications in Heat and Mass Transfer 140, 106552, 2023 | 2 | 2023 |
| Experimental investigation on the characteristics of molten lead-bismuth non-eutectic alloy fragmentation in water S Tan, Y Zhong, H Cheng, S Cheng Nuclear Science and Techniques 33 (9), 115, 2022 | 2 | 2022 |
| Numerical study on the release and migration behavior of fission gas in a molten LBE pool Z Mai, Z Zhao, H Cheng, S Cheng, J Zhao Frontiers in Energy Research 10, 2022 | 2 | 2022 |
| An innovation idea for SBLOCA mitigation strategy: Self-coagulation system in comparison with human hemostatic mechanism H Cheng, Z Mai, X Zhu, L Wang, J Wang Progress in Nuclear Energy, 2021 | 2 | 2021 |
| Chapter 19 - Lattice Boltzmann method code S Shimpei, H Cheng Nuclear Power Plant Design and Analysis Codes, 463-480, 2020 | 2* | 2020 |
