| A mixed core for supercritical water-cooled reactors X Cheng, XJ Liu, YH Yang Nuclear engineering and technology 40 (2), 117-126, 2008 | 105 | 2008 |
| Thermal-hydraulic and neutron-physical characteristics of a new SCWR fuel assembly XJ Liu, X Cheng Annals of Nuclear Energy 36 (1), 28-36, 2009 | 67 | 2009 |
| In-and ex-vessel coupled analysis of IVR-ERVC phenomenon for large scale PWR Y Jin, W Xu, X Liu, X Cheng Annals of Nuclear Energy 80, 322-337, 2015 | 52 | 2015 |
| Fluid-to-fluid scaling of heat transfer in circular tubes cooled with supercritical fluids X Cheng, XJ Liu, HY Gu Nuclear Engineering and Design 241 (2), 498-508, 2011 | 43 | 2011 |
| Online autonomous calibration of digital twins using machine learning with application to nuclear power plants H Song, M Song, X Liu Applied Energy 326, 119995, 2022 | 38 | 2022 |
| 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 | 38 | 2020 |
| Development of a sub-channel code for liquid metal cooled fuel assembly XJ Liu, N Scarpelli Annals of Nuclear Energy 77, 425-435, 2015 | 38 | 2015 |
| 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 | 36 | 2018 |
| 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 | 35 | 2019 |
| High-fidelity multi-physics coupling study on advanced heat pipe reactor W Xiao, X Li, P Li, T Zhang, X Liu Computer Physics Communications 270, 108152, 2022 | 34 | 2022 |
| Core and sub-channel analysis of SCWR with mixed spectrum core XJ Liu, T Yang, X Cheng Annals of Nuclear Energy 37 (12), 1674-1682, 2010 | 31 | 2010 |
| Computational fluid dynamics and subchannel analysis of lead–bismuth eutectic-cooled fuel assembly under various blockage conditions XJ Liu, DM Yang, Y Yang, X Chai, JB Xiong, TF Zhang, X Cheng Applied Thermal Engineering 164, 114419, 2020 | 30 | 2020 |
| Coupled thermal-hydraulics and neutron-physics analysis of SCWR with mixed spectrum core XJ Liu, X Cheng Progress in Nuclear Energy 52 (7), 640-647, 2010 | 30 | 2010 |
| Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes–PREMIUM benchmark T Skorek, A de Crécy, A Kovtonyuk, A Petruzzi, R Mendizábal, ... Nuclear Engineering and Design 354, 110199, 2019 | 29 | 2019 |
| VITAS: A multi-purpose simulation code for the solution of neutron transport problems based on variational nodal methods T Zhang, W Xiao, H Yin, Q Sun, X Liu Annals of Nuclear Energy 178, 109335, 2022 | 27 | 2022 |
| Research status and prospect of supercritical water-cooled reactor X Cheng Atomic Energy Science and Technology 42 (2), 167, 2008 | 27 | 2008 |
| Prediction of heat transfer to supercritical water at different boundary conditions X Cheng, M Zhao, F Feuerstein, XJ Liu International Journal of Heat and Mass Transfer 131, 527-536, 2019 | 25 | 2019 |
| Modification and application of the system analysis code ATHLET to trans-critical simulations SW Fu, XJ Liu, C Zhou, ZH Xu, YH Yang, X Cheng Annals of Nuclear Energy 44, 40-49, 2012 | 24 | 2012 |
| Gradient descent-particle swarm optimization based deep neural network predictive control of pressurized water reactor power DA Ejigu, X Liu Progress in Nuclear Energy 145, 104108, 2022 | 22 | 2022 |
| Research challenges of heat transfer to supercritical fluids X Cheng, XJ Liu Journal of Nuclear Engineering and Radiation Science 4 (1), 2018 | 21 | 2018 |
Jinbiao XiongProfessor, School of Nuclear Science and Engineering, Shanghai Jiao Tong University在 sjtu.edu.cn 的电子邮件经过验证
Jinbiao XiongProfessor, School of Nuclear Science and Engineering, Shanghai Jiao Tong University在 sjtu.edu.cn 的电子邮件经过验证
Meiqi SongShanghai Jiao Tong University在 sjtu.edu.cn 的电子邮件经过验证