| Liquid metal embrittlement of an Fe10Cr4Al ferritic alloy exposed to oxygen-depleted and-saturated lead-bismuth eutectic at 350° C X Gong, J Chen, F Hu, C Xiang, Z Yu, J Xiao, H Wang, H Gong, H Wang, ... Corrosion Science 165, 108364, 2020 | 36 | 2020 |
| Liquid metal embrittlement susceptibility of a high-entropy alloy exposed to oxygen-depleted liquid lead-bismuth eutectic at 250 and 350 C X Huang, X Gong, M Song, J Chen, F Hu, Y Yin, J Xiao, H Wang, H Wang, ... Journal of Nuclear Materials 528, 151859, 2020 | 30 | 2020 |
| Modification and application of water film model in COCOSYS for PWR's passive containment cooling X Huang, X Cheng Nuclear Engineering and Design 280, 251-261, 2014 | 18 | 2014 |
| Effect of temperature on liquid metal embrittlement susceptibility of an Fe10Cr4Al ferritic alloy in contact with stagnant lead-bismuth eutectic X Gong, F Hu, J Chen, H Wang, H Gong, J Xiao, H Wang, Y Deng, B Pang, ... Journal of Nuclear Materials 537, 152196, 2020 | 14 | 2020 |
| Removal of V (V) from solution using a silica-supported primary amine resin: batch studies, experimental analysis, and mathematical modeling X Huang, Z Ye, L Chen, X Chen, C Liu, Y Yin, X Wang, Y Wei Molecules 25 (6), 1448, 2020 | 14 | 2020 |
| Transient analysis of AP1000 NPP under the similar Fukushima accident conditions J Yang, R Liang, Z Lin, X Huang, T Wang Annals of Nuclear Energy 108, 181-187, 2017 | 12 | 2017 |
| Numerical investigation on LBE-water interaction for heavy liquid metal cooled fast reactors X Huang, P Chen, Y Yin, B Pang, Y Li, X Gong, Y Deng Nuclear Engineering and Design 361, 110567, 2020 | 11 | 2020 |
| Design and evaluation of an innovative LWR fuel combined dual-cooled annular geometry and SiC cladding materials Y Deng, M Liu, B Qiu, Y Yin, X Gong, X Huang, B Pang, Y Li Nuclear Engineering and Technology 53 (1), 178-187, 2021 | 10 | 2021 |
| Performance evaluation and efficiency enhancement of a space thermionic fuel element for thermal energy conversion and utilization Y Deng, B Qiu, K Lu, Y Yin, X Gong, B Pang, X Huang, Y Li, Y Wu, G Su Applied Thermal Engineering 173, 115237, 2020 | 10 | 2020 |
| Evaluation of passive containment cooling with an advanced water film model in a lumped-parameter code X Huang, X Cheng, W Klein-Heßling Nuclear Technology 196 (2), 248-259, 2016 | 10 | 2016 |
| Study of the integrated falling liquid film model in the containment code for nuclear safety evaluation X Huang, B Pang, Y Yin, X Cheng Progress in Nuclear Energy 127, 103429, 2020 | 7 | 2020 |
| Research on performance enhancement of nuclear fuel with SiC cladding by using high thermal conductivity fuels Y Deng, B Qiu, B Pang, X Gong, Y Wu, G Su, X Huang, Y Li, Y Yin Progress in Nuclear Energy 124, 103330, 2020 | 7 | 2020 |
| Effect of alloying elements on liquid metal embrittlement of pure BCC Fe in contact with liquid lead-bismuth eutectic: Experiments and first principles calculation X Gong, L Sun, F Zhang, Y Yin, X Huang, H Gong, Y Liu Corrosion Science 208, 110522, 2022 | 6 | 2022 |
| Mathematical analysis of heat balance model for the bubble growth in the subcooled boiling flow X Dong, Y Yu, Z Zhang, X Huang Case Studies in Thermal Engineering 28, 101630, 2021 | 5 | 2021 |
| Proposal of a turbulent Prandtl number model for Reynolds-averaged Navier–Stokes approach on the modeling of turbulent heat transfer of low-Prandtl number liquid metal X Huang, B Pang, X Chai, Y Yin Frontiers in Energy Research 10, 928693, 2022 | 4 | 2022 |
| Experimental Investigation on the Cleaning Effect and Influence Rule of Hydrogen Peroxide–Acetic Acid on Lead–Bismuth Eutectic Alloy X Huang, B Pang, X Zhou, Y Yin Frontiers in Energy Research 9, 735199, 2021 | 3 | 2021 |
| 堆外蒸汽爆炸堆腔压力冲量分布计算分析 黄熙， 杨燕华， 王溪 核动力工程 32 (3), 15-21, 2011 | 3 | 2011 |
| Removal of the Homolog Tellurium of Polonium by SiO2 Nanofiber Filter for Lead Alloy-Cooled Reactors X Chen, X Chen, X Zeng, Y Zhao, X Li, X Huang, T Fujita, X Wang Toxics 10 (6), 275, 2022 | 2 | 2022 |
| Effect of water addition into the precursor powders on microstructure and tensile mechanical properties of a Mo-0.5 La alloy X Gong, Y Zeng, X Fu, P Feng, X Huang Journal of Nuclear Materials 527, 151835, 2019 | 2 | 2019 |
| 使用 FCI-CMFD 软件分析岭澳二期核电厂直接安全壳加热事故 王溪， 杨燕华， 黄熙 原子能科学技术 44 (11), 1355-1360, 2010 | 2 | 2010 |
