| Experimental investigation on split-mixing-vane forced mixing in pressurized water reactor fuel assembly J Xiong, W Qu, T Zhang, X Chai, X Liu, Y Yang Annals of Nuclear Energy 143, 107450, 2020 | 46 | 2020 |
| CFD analysis of flow blockage phenomena in a LBE-cooled 19-pin wire-wrapped rod bundle X Chai, X Liu, J Xiong, X Cheng Nuclear Engineering and Design 344, 107-121, 2019 | 43 | 2019 |
| CFD simulation of swirling flow induced by twist vanes in a rod bundle J Xiong, R Cheng, C Lu, X Chai, X Liu, X Cheng Nuclear Engineering and Design 338, 52-62, 2018 | 39 | 2018 |
| Experimental study on transient heat transfer performance of high temperature heat pipe under temperature feedback heating mode for micro nuclear reactor applications J Deng, T Wang, X Liu, T Zhang, H He, X Chai Applied Thermal Engineering 230, 120826, 2023 | 23 | 2023 |
| Numerical investigation of thermal-hydraulic behaviors in a LBE-cooled 19-pin wire-wrapped rod bundle X Chai, X Liu, J Xiong, X Cheng Progress in Nuclear Energy 119, 103044, 2020 | 23 | 2020 |
| Numerical investigation of flow blockage accident in SFR fuel assembly X Chai, L Zhao, W Hu, Y Yang, X Liu, J Xiong, X Cheng Nuclear Engineering and Design 359, 110437, 2020 | 20 | 2020 |
| Multi-physics coupled simulation on steady-state and transients of heat pipe cooled reactor system T Li, J Xiong, T Zhang, X Chai, X Liu Annals of Nuclear Energy 187, 109774, 2023 | 17 | 2023 |
| Conceptual design and thermal-hydraulic analysis of a megawatt-level lead-bismuth cooling reactor for deep-sea exploration Q Yang, Q Sun, X Liu, H He, T Zhang, X Chai, Y Luo Progress in Nuclear Energy 145, 104125, 2022 | 17 | 2022 |
| Preliminary lightweight core design analysis of a micro‐transportable gas‐cooled thermal reactor C Guan, X Chai, T Zhang, X Liu International Journal of Energy Research 46 (12), 17416-17428, 2022 | 16 | 2022 |
| Predictions of quench temperature and quench velocity in narrow rectangular channel of novel plate-type reactor W Xu, J Guo, X Liu, J Xiong, X Chai, T Zhang, X Cheng, W Zeng Annals of Nuclear Energy 131, 148-155, 2019 | 16 | 2019 |
| Development of 3D transient neutronics and thermal-hydraulics coupling procedure and its application to a fuel pin analysis Q Xie, W Li, C Guan, Q Sun, X Chai, X Liu Nuclear Engineering and Design 404, 112164, 2023 | 15 | 2023 |
| Wake acceleration effect on spherical bubbles aligned in-line X Chai, X Cheng Progress in Nuclear Energy 80, 74-79, 2015 | 14 | 2015 |
| Investigations of multiphysics models on a megawatt-level heat pipe nuclear reactor based on high-fidelity approaches J Zhang, T Li, Z Shen, X Li, J Xiong, X Chai, X Liu, T Zhang Nuclear Science and Engineering 198 (5), 1097-1121, 2024 | 13 | 2024 |
| Mass and efficiency optimization of a He-Xe Brayton cycle for mobile, land-based nuclear microreactors C Guan, X Chai, T Zhang, X Liu, H He Energy Conversion and Management 301, 118011, 2024 | 13 | 2024 |
| A discrete-ordinates variational nodal method for heterogeneous neutron Boltzmann transport problems Q Sun, X Liu, X Chai, H He, T Zhang Computers & Mathematics with Applications 170, 142-160, 2024 | 12 | 2024 |
| Evaluation of start-up characteristics for heat pipe-cooled nuclear reactor coupled with recuperated open-air brayton cycle using hardware-in-the-loop J Deng, C Guan, T Wang, X Liu, X Chai Energy 301, 131698, 2024 | 12 | 2024 |
| Coupling of neutronics and thermal-hydraulics codes for the simulation of reactivity insertion accident for LFR D Yang, X Liu, J Xiong, X Chai, X Cheng Progress in Nuclear Energy 106, 20-26, 2018 | 12 | 2018 |
| 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 | 11 | 2022 |
| Conceptual design of an innovative reduced moderation thorium‐fueled small modular reactor with heavy‐water coolant T Zhang, J Xiong, X Liu, X Chai, W Li, X Cheng International Journal of Energy Research 43 (14), 8286-8298, 2019 | 10 | 2019 |
| Preliminary conceptual design of a moderated micro nuclear reactor core cooled by heat pipe X Chai, C Guan, J Deng, T Zhang, X Liu Annals of Nuclear Energy 179, 109399, 2022 | 9 | 2022 |
