Suizheng Qiu

Anhui University of Science and Technology — China

Engineering · Physical Sciences

51h-index15.8kcitations1.2kworks2.52yr avg
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Research Topics

Nuclear reactor physics and engineering(578), Nuclear Engineering Thermal-Hydraulics(486), Nuclear Materials and Properties(423), Heat Transfer and Boiling Studies(234), Heat transfer and supercritical fluids(172)

Publications1.2k total

Highly accurate and interpretable machine learning models for predicting HTC in the presence of NCG on outer vertical tubes
Progress in Nuclear Energy·2025· 1 cited
Experimental study on the heat transfer characteristics of a lead-bismuth/heat pipe heat exchange prototype for liquid metal matrix-based heat pipe-cooled microreactors
Nuclear Engineering and Design·2025
Microstructure evolution of molten zirconium oxidative solidification: Experiment and numerical simulation
Materials & Design·2025· 1 citedOpen Access
Experimental investigation of heat transfer and friction characteristics of high-pressure helium with variable properties in circular tubes
International Journal of Thermal Sciences·2025
Safety characteristic analysis driven by machine learning algorithm for an offshore nuclear energy system
Progress in Nuclear Energy·2025
Numerical study of spray cooling: The effect of nozzle arrangement on heat transfer performance
International Journal of Multiphase Flow·2025· 1 cited
Transient thermal–hydraulic characteristics of the lithium loop in space lithium-cooled fast reactor
Nuclear Engineering and Design·2025
Design parameters sensitivity analysis of dispersed plate-type nuclear fuel in Reactivity Insertion Accident
Nuclear Engineering and Design·2025
Numerical and experimental investigations on time-varying dynamic characteristics of three-point contact ball bearings
Mechanism and Machine Theory·2025
Integrating Particle Method Simulations and Machine Learning for Predicting Core Melt Flow Pattern
Springer proceedings in physics·2025
Numerical Simulation of Foreign Object Motion on Secondary Side of Steam Generator Tube Zone
Springer proceedings in physics·2025
Performance evaluation and adaptive variable-order method of thermal-hydraulic simulations models based on random forests
Annals of Nuclear Energy·2025
Numerical Simulation of Flooding Pathways in Nuclear Power Plants by Coupling a Porous Media Model with LSMPS
Springer proceedings in physics·2025
Numerical study on material behavior and core temperature field evolution under CDAs in LFR
Nuclear Engineering and Technology·2025· 1 citedOpen Access
Coupling analysis of thermoelectric characteristics of power generation module in PWR nuclear power plant
Nuclear Techniques·2025Open Access
Sodium side inlet flow distribution characteristics of the steam generator in China demonstration fast reactor
Nuclear Techniques·2025Open Access
Mixed convection in horizontal channel with unstable stratification for low-Prandtl-number fluids
Physics of Fluids·2025· 10 cited
Experimental investigation on natural circulation characteristics of symmetric dual loop under motion conditions
Applied Thermal Engineering·2025
Conceptual design of heat pipe cooled reactor with liquid sodium core for space power systems
Progress in Nuclear Energy·2025
A multi-task Transformer-Mamba-Seq framework for real-time estimation of spatiotemporal thermal stratification in passive residual heat exchanger
International Communications in Heat and Mass Transfer·2025
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Frequent Co-authors

Wenxi Tian(39), G.H. Su(37), Dalin Zhang(18), Chenglong Wang(18), Mingjun Wang(11), G.H. Su(6), Yapei Zhang(5), Simiao Tang(5), Wenxi Tian(5), Guanghui Su(3), Tenglong Cong(3), Yingwei Wu(3), Kailun Guo(3), Hao Sun(3), Yingjie Wang(2), Limin Liu(2), Minghao Liu(2), Shibao Wang(2), Xiao Liu(2), Luteng Zhang(2)