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Yujie Dong
Yujie Dong
在 tsinghua.edu.cn 的电子邮件经过验证
标题
引用次数
引用次数
年份
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
6062009
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
3192016
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
942009
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
602017
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
462018
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
462017
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
422018
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
412019
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
402009
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
362017
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
312017
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
302022
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
292020
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
252017
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
252016
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
242018
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
242016
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
222015
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
212016
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
202017
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