| Current status and technical description of Chinese 2× 250 MWth HTR-PM demonstration plant Z Zhang, Z Wu, D Wang, Y Xu, Y Sun, F Li, Y Dong Nuclear Engineering and Design 239 (7), 1212-1219, 2009 | 618 | 2009 |
| The Shandong Shidao Bay 200 MWe high-temperature gas-cooled reactor pebble-bed module (HTR-PM) demonstration power plant: an engineering and technological innovation Z Zhang, Y Dong, F Li, Z Zhang, H Wang, X Huang, H Li, B Liu, X Wu, ... Engineering 2 (1), 112-118, 2016 | 335 | 2016 |
| Thermohydraulic transient studies of the Chinese 200 MWe HTR-PM for loss of forced cooling accidents Y Zheng, L Shi, Y Dong Annals of Nuclear Energy 36 (6), 742-751, 2009 | 94 | 2009 |
| Model-free adaptive control law for nuclear superheated-steam supply systems Z Dong, Y Pan, Z Zhang, Y Dong, X Huang Energy 135, 53-67, 2017 | 62 | 2017 |
| Dynamical modeling and simulation of the six-modular high temperature gas-cooled reactor plant HTR-PM600 Z Dong, Y Pan, Z Zhang, Y Dong, X Huang Energy 155, 971-991, 2018 | 48 | 2018 |
| Experimental investigation on gas-solid hydrodynamics of coarse particles in a two-dimensional spouted bed H Zhang, M Liu, T Li, Z Huang, X Sun, H Bo, Y Dong Powder Technology 307, 175-183, 2017 | 47 | 2017 |
| Multi-layer perception based model predictive control for the thermal power of nuclear superheated-steam supply systems Z Dong, Z Zhang, Y Dong, X Huang Energy 151, 116-125, 2018 | 43 | 2018 |
| Dynamical modeling and simulation analysis of a nuclear desalination plant based on the MED-TVC process Z Dong, M Liu, X Huang, Y Zhang, Z Zhang, Y Dong Desalination 456, 121-135, 2019 | 42 | 2019 |
| Benchmark calculation for the steady-state temperature distribution of the HTR-10 under full-power operation F Chen, Y Dong, Y Zheng, L Shi, Z Zhang Journal of Nuclear Science and Technology 46 (6), 572-580, 2009 | 40 | 2009 |
| Experimental research on the radioactive dust in the primary loop of HTR-10 F Xie, J Cao, X Feng, X Liu, J Tong, H Wang, Y Dong, Z Zhang, ... Nuclear Engineering and Design 324, 372-378, 2017 | 37 | 2017 |
| 600-MWe high-temperature gas-cooled reactor nuclear power plant HTR-PM600 ZY Zhang, YJ Dong, Q Shi, F Li, HT Wang Nuclear Science and Techniques 33 (8), 101, 2022 | 36 | 2022 |
| Air ingress analysis of chimney effect in the 200 MWe pebble-bed modular high temperature gas-cooled reactor Z Chen, X Chen, Y Zheng, J Sun, F Chen, L Shi, F Li, Y Dong, Z Zhang Annals of Nuclear Energy 106, 143-153, 2017 | 32 | 2017 |
| Multilayer perception based reinforcement learning supervisory control of energy systems with application to a nuclear steam supply system Z Dong, X Huang, Y Dong, Z Zhang Applied Energy 259, 114193, 2020 | 31 | 2020 |
| Effects of reaction temperature and inlet oxidizing gas flow rate on IG-110 graphite oxidation used in HTR-PM X Sun, Y Dong, Y Zhou, Z Li, L Shi, Y Sun, Z Zhang Journal of Nuclear Science and Technology 54 (2), 196-204, 2017 | 27 | 2017 |
| Study on air ingress of the 200 MWe pebble-bed modular high temperature gas-cooled reactor P Liu, Z Chen, Y Zheng, J Sun, F Chen, L Shi, F Li, Y Dong, Z Zhang Annals of Nuclear Energy 98, 120-131, 2016 | 26 | 2016 |
| Experimental study on plug formation characteristics of a novel draft tube type feeder for vertical pneumatic conveying of coarse particles H Zhang, M Liu, T Li, Z Huang, H Bo, Y Dong Powder Technology 301, 730-736, 2016 | 26 | 2016 |
| Study of tritium in the primary loop of HTR-10: Experiment and theoretical calculations F Xie, J Cao, X Feng, J Tong, Y Dong, Z Zhang, RO Scarlat Progress in Nuclear Energy 105, 99-105, 2018 | 25 | 2018 |
| Design and study of radioactive graphite dust experimental system in primary loop of HTR-10 F Xie, J Cao, Z Chen, Y Dong Atomic Energy Science and Technology 49 (4), 744-749, 2015 | 22 | 2015 |
| Numerical simulation on heat transfer process in the reactor cavity of modular high temperature gas-cooled reactor H Zhao, Y Dong, Y Zheng, T Ma, X Chen Applied Thermal Engineering 125, 1015-1024, 2017 | 21 | 2017 |
| Post-test simulation of the HTR-10 reactivity insertion without scram F Chen, Y Dong, Z Zhang Annals of Nuclear Energy 92, 36-45, 2016 | 21 | 2016 |
