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Author

Huaping Mei

Observed name: Hua-ping Mei
ORCID: 0000-0002-8233-6223
Observed ORCID: 0000-0002-8233-6223
OpenAlex ID: A5062378636
Conceptual design for a 5 kWe space nuclear reactor power system
2024 · Huaping Mei, Dali Yu, et al. · Nuclear Engineering and Technology · 18
Key features and highly effective prediction of complete startup from frozen state for high-temperature heat pipe in heat pipe reactor
2023 · Dali Yu, Jian Liu, et al. · Applied Thermal Engineering · 15
Study of the thermal expansion effects of a space nuclear reactor with an integrated honeycomb core design using OpenMC and ANSYS
2023 · Chao Chen, Huaping Mei, et al. · Annals of Nuclear Energy · 12
Numerical simulation analysis of high-temperature bent sodium heat pipes
2024 · Xiongwei Cheng, Hualei Jiang, et al. · Kerntechnik · 5
An improved two-temperature method for computing the temperature distributions within a TRISO-coated particle pebble fuel
2025 · Dali Yu, Fangnian Wang, et al. · Nuclear Engineering and Technology · 4
CFD investigation on thermal hydraulics of the double-wall bayonet tube heat exchanger in CLEAR-S facility
2022 · Shuyong Liu, Fan Xia, et al. · Annals of Nuclear Energy · 4
Design of high-temperature sodium heat pipe with composite wick based on non-dominated sorting genetic algorithm (NSGA)
2024 · Jian-song Zhang, Hua-ping Mei, et al. · Nuclear Engineering and Technology · 3
Advancing the safety design of heat pipe cooled reactors: a case study of lead liquid bath and monolith stainless steel core
2025 · Taiwo Saheed Yinusa, Huaping Mei, et al. · Kerntechnik · 2
Feasibility assessment of heat pipe space reactor passive start-up without external neutron source
2022 · Chao Chen, Zhen Wang, et al. · Annals of Nuclear Energy · 2
Research on the effect of the key parameters on heat transfer capacity of sodium heat pipe based on COMSOL
2026 · Jiansong Zhang, Huaping Mei, et al. · International Communications in Heat and Mass Transfer · 1
Mechanistic study on ion irradiation-induced cracking behavior of zirconium hydride
2026 · Xingyu Jiang, Jiansong Zhang, et al. · Journal of Materials Science · 1
Core design and neutronics analysis of lead liquid metal-based heat pipe cooled reactor for undersea purpose
2024 · Taiwo Saheed Yinusa, Huaping Mei, et al. · Kerntechnik · 1
Transient thermal performance and safety assessment of a liquid lead heat pipe cooled microreactor
2026 · Taiwo Saheed Yinusa, Huaping Mei, et al. · Progress in Nuclear Energy
Computer vision-based detection and dynamic tracking of multiple micro bubbles in transparent liquid similarity experiments for SGTR in lead-cooled fast reactor
2026 · Ying Guan, Yang Li, et al. · Annals of Nuclear Energy
Research on Sodium Heat Pipe with Composite Wick under Staged Power Startup (SPS) and Direct High-Power Startup (DHPS) across Full Inclination Angles
2026 · Jiansong Zhang, Kaibao Liu, et al. · SSRN Electronic Journal
Study on the effects of 135Xe and 149Sm on reactivity in megawatt-level heat pipe reactors
2024 · Mingzhen Wu, Huaping Mei, et al. · Journal of Radioanalytical and Nuclear Chemistry
Thermal-hydraulic analysis of lead-bismuth cooled reactors core based on single channel model
2024 · Shuyong Liu, Huaping Mei, et al. · International Journal of Nuclear Energy Science and Technology
Thermal-hydraulic analysis of lead-bismuth cooled reactors core based on single channel model
2024 · Huaping Mei, Shuyong Liu, et al. · International Journal of Nuclear Energy Science and Technology
Modal Analysis of Fuel Assembly for CLEAR-I
2015 · Qingsheng Wu, Qian Peng Han, et al. · NCSU Libraries Repository (North Carolina State University Libraries)
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Works count: 19
Citation count: 68
H-index: 4
I10-index: 3
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