| Review of conceptual design and fundamental research of molten salt reactors in China D Zhang, L Liu, M Liu, R Xu, C Gong, J Zhang, C Wang, S Qiu, G Su International Journal of Energy Research 42 (5), 1834-1848, 2018 | 122 | 2018 |
| Experimental investigation of flow and convective heat transfer on a high-Prandtl-number fluid through the nuclear reactor pebble bed core L Liu, D Zhang, L Li, Y Yang, C Wang, S Qiu, GH Su Applied Thermal Engineering 145, 48-57, 2018 | 35 | 2018 |
| Preliminary neutronic and thermal-hydraulic analysis of a 2áMW Thorium-based Molten Salt Reactor with Solid Fuel L Liu, D Zhang, Q Lu, K Wang, S Qiu Progress in nuclear energy 86, 1-10, 2016 | 33 | 2016 |
| The role of nuclear energy in the carbon neutrality goal L Liu, H Guo, L Dai, M Liu, Y Xiao, T Cong, H Gu Progress in Nuclear Energy 162, 104772, 2023 | 32 | 2023 |
| Experimental analysis of flow and convective heat transfer in the water-cooled packed pebble bed nuclear reactor core L Liu, J Deng, D Zhang, C Wang, S Qiu, GH Su Progress in Nuclear Energy 122, 103298, 2020 | 26 | 2020 |
| Conceptual design and analysis of heat pipe cooled silo cooling system for the transportable fluoride-salt-cooled high-temperature reactor C Wang, L Liu, M Liu, D Zhang, W Tian, S Qiu, GH Su Annals of Nuclear Energy 109, 458-468, 2017 | 18 | 2017 |
| Preliminary thermal and mechanical analysis on the reactor core of a new heat pipe cooled reactor applied in the underwater environment L Liu, B Liu, Y Xiao, H Gu, H Guo Progress in Nuclear Energy 150, 104306, 2022 | 16 | 2022 |
| Review of the experimental research on the thermal‐hydraulic characteristics in the pebble bed nuclear reactor core and fusion breeder blankets L Liu, J Deng, D Zhang, H Gu International Journal of Energy Research 45 (8), 11352-11383, 2021 | 15 | 2021 |
| Scaling and distortion analysis using a simple natural circulation loop for FHR development L Liu, P Peterson, D Zhang, I Johnson, S Qiu, GH Su Applied Thermal Engineering 168, 114849, 2020 | 15 | 2020 |
| RELAP5 MOD3. 2 modification and application to the transient analysis of a fluoride-salt-cooled high-temperature reactor L Liu, D Zhang, Q Yan, R Xu, C Wang, S Qiu, GH Su Annals of Nuclear Energy 101, 504-515, 2017 | 15 | 2017 |
| Modification and application of Relap5 Mod3 code to several types of nonwater‐cooled advanced nuclear reactors L Liu, D Zhang, J Song, C Wang, X Gao, W Tian, S Qiu, GH Su International Journal of Energy Research 42 (1), 221-235, 2018 | 13 | 2018 |
| Influence of helix angle on flow and heat transfer characteristics of lead–bismuth flow in helical-coiled tube bundles C Shen, L Liu, Z Xu, H Gu, M Liu Annals of Nuclear Energy 180, 109483, 2023 | 11 | 2023 |
| Experimental investigation on pressure drop of a PWR fuel assembly under low Re conditions M Liu, L Wang, S Ni, X Wang, L Liu, H Gu Annals of Nuclear Energy 167, 108768, 2022 | 9 | 2022 |
| 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 | 9 | 2022 |
| Neutronics/thermal-hydraulics coupling analysis for the liquid-fuel MOSART concept D Zhang, L Liu, M Liu, R Xu, C Gong, S Qiu Energy Procedia 127, 343-351, 2017 | 8 | 2017 |
| Development of heat transfer correlation of turbulent forced convection in subchannels with rough surfaces based on CFD X Wang, C Shen, L Liu, M Liu, H Gu Annals of Nuclear Energy 181, 109542, 2023 | 6 | 2023 |
| Experimental study on the natural circulation behavior of a full-scale PWR fuel assembly M Liu, S Ni, X Wang, L Liu, H Gu Annals of nuclear energy 174, 109172, 2022 | 6 | 2022 |
| Study on two-phase flow instability of parallel helical tubes in steam generator of small modular reactors C Shen, M Liu, Z Xu, K Cheng, L Liu, H Gu International Communications in Heat and Mass Transfer 148, 107023, 2023 | 5 | 2023 |
| Coupled neutronics/thermal-hydraulics and safety characteristics of liquid-fueled Molten Salt Reactors S Qiu, D Zhang, L Liu, M Liu, R Xu, C Gong, GH Su Kerntechnik 81 (2), 149-159, 2016 | 5 | 2016 |
| 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 | 4 | 2022 |
