Crack fault diagnosis of rotating machine in nuclear power plant based on ensemble learning X Zhong, H Ban Annals of Nuclear Energy 168, 108909, 2022 | 30 | 2022 |
Pre-trained network-based transfer learning: A small-sample machine learning approach to nuclear power plant classification problem X Zhong, H Ban Annals of Nuclear Energy 175, 109201, 2022 | 28 | 2022 |
An improved method for hydrogen deflagration to detonation transition prediction under severe accidents in nuclear power plants X Zhang, J Yu, T Huang, G Jiang, X Zhong, M Saeed International Journal of Hydrogen Energy 44 (21), 11233-11239, 2019 | 25 | 2019 |
Development of an improved non-equilibrium multi-region model for pressurized water reactor pressurizer X Zhong, X Zhang, J Yu, M Saeed, Y Li, Z Chen, B Tang, Y Sun Annals of Nuclear Energy 126, 133-141, 2019 | 18 | 2019 |
Deep reinforcement learning for class imbalance fault diagnosis of equipment in nuclear power plants X Zhong, L Zhang, H Ban Annals of Nuclear Energy 184, 109685, 2023 | 15 | 2023 |
Development of a plug-and-play anti-noise module for fault diagnosis of rotating machines in nuclear power plants X Zhong, F Wang, H Ban Progress in Nuclear Energy 151, 104344, 2022 | 13 | 2022 |
Analysis of degassing time of pressurized water reactor pressurizer X Zhong, J Yu, X Guo, M Saeed Nuclear Engineering and Design 328, 301-308, 2018 | 5 | 2018 |
Comparative study on water thermodynamic property functions of TRACE code X Zhong, X Zhang, M Saeed, Z Li, J Yu Annals of Nuclear Energy 147, 107754, 2020 | 4 | 2020 |
Analysis of wall temperature jump of China Generation IV SFR Steam Generator X Zhong, J Yu, S Yan, M Saeed, Y Li Annals of Nuclear Energy 114, 510-517, 2018 | 3 | 2018 |
Development of a seven-region lumped parameter nonlinear dynamic model for U-tube recirculation nuclear steam generator X Zhong, P Guo, X Zhang, M Saeed, H Ma, J Huang, J Yu Annals of Nuclear Energy 174, 109190, 2022 | 2 | 2022 |
Development of a lumped parameter dynamic degassing model for spray-heating degasser and its application in the pressurizer of a pressurized water reactor X Zhong, J Yu, X Zhang, M Saeed, Y Li, Z Chen, B Tang, Y Sun, T Huang Nuclear Technology 207 (2), 228-246, 2021 | 2 | 2021 |
Analysis of Hydrodynamic Characteristic in Straight-Tube Sodium-Heated Once-Through Steam Generator X Zhong, J Yu, M Saeed, C Yang, X Zhang International Conference on Nuclear Engineering 57847, V006T08A014, 2017 | 1 | 2017 |
Uncertainty and sensitivity analysis of numerical simulation results of hydrogen recombiner case B Hou, J Yu, X Zhong, G Jiang, Z Zou Nuclear Power Engineering 37 (3), 80-86, 2016 | 1 | 2016 |
Guidance of nuclear power plant code development X Zhong Nuclear Power Plant Design and Analysis Codes, 23-54, 2021 | | 2021 |
Performance Analysis of Ensemble Learning in Bearing Fault Diagnosis of Rotating Machines X Zhong, DG Cole, H Ban Transactions of the American Nuclear Society 123 (2020), 2020 | | 2020 |