| Enhancement of mechanical, tribological and morphological properties of nitrogenated diamond-like carbon films by gradient nitrogen doping C Zeng, Q Chen, M Xu, S Deng, Y Luo, T Wu Diamond and Related Materials 76, 132-140, 2017 | 25 | 2017 |
| Preliminary control strategies of megawatt-class gas-cooled space nuclear reactor with different control rod configurations T Meng, K Cheng, C Zeng, Y He, S Tan Progress in Nuclear Energy 113, 135-144, 2019 | 22 | 2019 |
| Comparison on the thermal–hydraulic characteristics of wire-wrapped fuel and helical cruciform fuel by numerical simulation Q Zhang, T Cong, Y Xiao, J Li, C Zeng, H Gu Annals of Nuclear Energy 177, 109291, 2022 | 20 | 2022 |
| Experimental study on heat transfer and pressure drop characteristics in a microchannel heat exchanger assembly with S-shaped fins C Zeng, Y Song, X Zhou, F Zhang, M Jiao, M Liu, H Gu Applied Thermal Engineering 210, 118406, 2022 | 16 | 2022 |
| Experimental study on heat transfer and flow resistance performance of a microchannel heat exchanger with zigzag flow channels X Zhou, C Zeng, Y Song, M Jiao, F Zhang, M Liu Progress in Nuclear Energy 147, 104190, 2022 | 13 | 2022 |
| Neutronics analysis of megawatt-class gas-cooled space nuclear reactor design T Meng, F Zhao, K Cheng, C Zeng, S Tan Journal of Nuclear Science and Technology 56 (12), 1120-1129, 2019 | 13 | 2019 |
| Application of droplet motion and phase change model in containment spray system F Zhao, X Yan, H Bo, T Meng, C Zeng, S Tan Annals of Nuclear Energy 131, 123-137, 2019 | 13 | 2019 |
| Effect of SiNx interlayer thickness on adhesion and friction properties of diamond-like carbon films Q Chen, C Zeng, M Xu, H Yuan, H Lv, Z Wang, X Wang Diamond and Related Materials 94, 186-193, 2019 | 13 | 2019 |
| Optimization of the TRISO fuel particle distribution based on octahedral and icosahedral-based segmentation methods in the pebble-bed nuclear core M Liu, C Zeng, Z Luo, H Gu, J Deng International Journal of Advanced Nuclear Reactor Design and Technology 2 …, 2020 | 12 | 2020 |
| Performance evaluation of DRACS system of molten salt reactors using a transient solidification model C Zeng, X Chu, L Liu, M Liu, H Gu Nuclear Engineering and Design 386, 111565, 2022 | 11 | 2022 |
| A simplified method for calculating the heat rejection from a rectangle droplet sheet C Zeng, S Tan, S Qiao, F Zhao, T Meng International Journal of Heat and Mass Transfer 132, 762-771, 2019 | 11 | 2019 |
| Optimization of the thermal-hydraulic performance of zigzag-type microchannel heat exchangers using asymmetric geometry C Zeng, Y Song, X Zhou, F Zhang, M Chao, M Jiao, M Liu, H Gu Applied Thermal Engineering 217, 119216, 2022 | 6 | 2022 |
| Evaluation of a freeze-tolerant decay heat removal system redundancy for fluoride salt-cooled high-temperature reactors (FHR) M Liu, C Zeng, L Liu, H Gu Annals of Nuclear Energy 165, 108681, 2022 | 5 | 2022 |
| Application of droplet motion and evaporation model in fuel spray in the constant volume bomb T Meng, X Yan, F Zhao, H Bo, C Zeng, S Tan Journal of Thermal Science and Technology 14 (1), JTST0003-JTST0003, 2019 | 4 | 2019 |
| Development and validation of a one-dimensional solidification model—Part I: Analytical model C Zeng, M Liu, W Zhang, L Liu, L Liu, H Gu Annals of Nuclear Energy 193, 110057, 2023 | 3 | 2023 |
| Numerical simulation of inherent boric mixing phenomenon inside reactor annular down-comer Q Zhang, L Liu, Y Zeng, C Zeng, H Gu Progress in Nuclear Energy 148, 104230, 2022 | 3 | 2022 |
| Development and validation of a one-dimensional solidification model—Part II: Model validation for molten lead-bismuth C Zeng, M Liu, W Zhang, L Liu, L Liu, H Gu Annals of Nuclear Energy 193, 110058, 2023 | 2 | 2023 |
| Numerical investigation of the external emergency coolant transportation inside reactor annular down-comer Y Zeng, Q Zhang, H Chen, P Ming, S Liu, C Zeng Annals of Nuclear Energy 187, 109780, 2023 | 2 | 2023 |
| Droplet motion and phase change model with two-way coupling F Zhao, Q Liu, X Yan, H Bo, C Zeng, S Tan Journal of Thermal Science 28, 826-833, 2019 | 2 | 2019 |
| Development of friction factor and heat transfer correlation of liquid metal flow in helical tube bundles C Shen, M Liu, L Liu, Z Xu, C Zeng, L Liu, H Gu Annals of Nuclear Energy 201, 110442, 2024 | 1 | 2024 |
