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Minghao Liu

Review of conceptual design and fundamental research of molten salt reactors in China
2018 · Dalin Zhang, Limin Liu, et al. · International Journal of Energy Research · 138
MMAR: A Challenging Benchmark for Deep Reasoning in Speech, Audio, Music, and Their Mix
2025 · Ziyang Ma, Yinghao Ma, et al. · neural information processing systems · 137
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Evaluation of technical and gamma radiation shielding properties of sustainable ultra-high performance geopolymer concrete
2024 · Daquan Shi, Yan Xia, et al. · Construction and Building Materials · 89
Experimental study on heat transfer limit of high temperature potassium heat pipe for advanced reactors
2020 · Chenglong Wang, Xiao Liu, et al. · Annals of Nuclear Energy · 69
EasyMetagenome: A user‐friendly and flexible pipeline for shotgun metagenomic analysis in microbiome research
2025 · Defeng Bai, Tong Chen, et al. · iMeta · 59
Iron-rich industrial waste enhanced low-carbon radiation shielding functional composites
2024 · Yan Xia, Daquan Shi, et al. · Journal of Cleaner Production · 49
Valorization of steel slag into sustainable high-performance radiation shielding concrete
2024 · Daquan Shi, Yan Xia, et al. · Journal of Building Engineering · 38
Automatic Dataset Construction (ADC): Sample Collection, Data Curation, and Beyond
2024 · Liu, Minghao, Di, Zonglin, et al. · arXiv (Cornell University) · 24
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Experimental study on transient performance of heat pipe-cooled passive residual heat removal system of a molten salt reactor
2019 · Chenglong Wang, Minghao Liu, et al. · Progress in Nuclear Energy · 20
Conceptual design and analysis of heat pipe cooled silo cooling system for the transportable fluoride-salt-cooled high-temperature reactor
2017 · Chenglong Wang, Limin Liu, et al. · Annals of Nuclear Energy · 19
Experimental study on heat transfer performance between fluoride salt and heat pipes in the new conceptual passive residual heat removal system of molten salt reactor
2018 · Minghao Liu, Dalin Zhang, et al. · Nuclear Engineering and Design · 15
Experimental study on the heat transfer characteristics of fluoride salt in the new conceptual passive heat removal system of molten salt reactor
2018 · Minghao Liu, Dalin Zhang, et al. · International Journal of Energy Research · 13
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Design and evaluation of an innovative LWR fuel combined dual-cooled annular geometry and SiC cladding materials
2020 · Yangbin Deng, Minghao Liu, et al. · Nuclear Engineering and Technology · 12
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Code development and analysis of heat pipe cooled passive residual heat removal system of Molten salt reactor
2020 · Chenglong Wang, Qianni Duan, et al. · Annals of Nuclear Energy · 9
Transient thermal‐hydraulic analysis of heat pipe cooled passive residual heat removal system of molten salt reactor
2020 · Chenglong Wang, Yupeng Yang, et al. · International Journal of Energy Research · 8
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Temperature dependence of AC / DC breakdown strength of HVDC XLPE cable slices
2016 · Liu Xia, Yu Qinxue, et al. · International Conference on Condition Monitoring and Diagnosis (CMD) · 8
Neutronics/Thermal-hydraulics Coupling Analysis for the Liquid-Fuel MOSART Concept
2017 · Dalin Zhang, Limin Liu, et al. · Energy Procedia · 6
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Evaluation of typical interfacial area transport models for bubbly flow
2019 · Hang Liu, Jianyong Lai, et al. · International Journal of Advanced Nuclear Reactor Design and Technology · 5
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Synthesis and luminescence properties of LiY(WO4)2:Bi3+ broadband yellow-emitting phosphor for high-quality NUV pumped WLEDs
2025 · Xiaoqi Liu, Hongfei Li, et al. · Optical Materials · 2
Analysis of SMR Reactor Coolant System in APROS
2024 · Zhu Ye, Wang Xinbo, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
Jamming-free Impedance Control of UVMS Based on Contact Mechanisms for Peg-in-Hole Tasks
2024 · Haoyu Liu, Min Yu, et al. · Chinese Control and Decision Conference (CCDC)
Smr Feedwater System Analysis
2023 · Ye Zhu, Qiao Liang, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE)
CFD Analysis on the Small Module Reactor (ACP100) PRS Return Line Thermal Stratification Phenomenon
2022 · Li Peiying, Zhiyun Cai, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Interfacial Area Transport Model for Bubbly Flow System in Vertical Rod Bundle With Spacer Grids
2020 · Hang Liu, Jianyong Lai, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Simulation Analysis on the Pressurizer Degassing Sub-System of Module Small Reactor (ACP100)
2020 · Cai Zhiyun, Ren Yun, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Works count: 27
Citation count: 721
H-index: 12
I10-index: 13
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