G.H. Su

Jishou University — China

Engineering · Physical Sciences

22h-index1.6kcitations117works5.02yr avg
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Research Topics

Nuclear reactor physics and engineering(52), Nuclear Materials and Properties(50), Nuclear Engineering Thermal-Hydraulics(27), Heat Transfer and Boiling Studies(14), Metallurgical Processes and Thermodynamics(11)

Publications117 total

An assessment method for mega-constellation networks based on connected component calculation
Journal of Physics Conference Series·2025Open Access
Study on eutectic melting and high-temperature oxidation characteristics of Cr coated Zr alloy cladding under steam atmosphere at 1400–1500 °C
Journal of Alloys and Compounds·2025· 8 cited
MSPhys: multiscale fusing-based diffusion model for remote physiological measurement
Machine Vision and Applications·2025· 1 cited
Identifying Prompted Artist Names from Generated Images
arXiv (Cornell University)·2025Open Access
Simultaneous monitoring of oxygen and carbon monoxide based on TDLAS
Journal of Physics Conference Series·2025Open Access
Thermal-mechanical coupling behavior analysis of solid-state constrained component in advanced nuclear energy system
Energy·2025· 2 cited
MAGI-1: Autoregressive Video Generation at Scale
arXiv (Cornell University)·2025Open Access
Numerical simulation on thermal-hydraulic-mechanical coupling of core corium migration during severe accidents
Nuclear Engineering and Design·2025· 1 cited
Compromised Agency in the Subjective Experiences of Temporal Distortions Among Institutionalized Alzheimer’s Patients in China: A Qualitative Study
Qualitative Health Research·2025· 1 cited
PhysDiff: Physiology-based Dynamicity Disentangled Diffusion Model for Remote Physiological Measurement
Proceedings of the AAAI Conference on Artificial Intelligence·2025· 2 citedOpen Access
Comprehensive analysis of dual-heat-source Brayton cycle
Applied Thermal Engineering·2025
Research status in safety analysis of steam generator tube rupture accident in lead-based fast reactors – A review
Nuclear Engineering and Design·2025· 20 cited
High-temperature oxidation of accident tolerant Cr-coated Zr alloy cladding: Model development and validation
Journal of Nuclear Materials·2025· 8 cited
Simulation and Verification of PCI Behavior in SiC f/SiC Composite Cladding Fuel Elements Based on Finite Element Analysis Method
SSRN Electronic Journal·2025Open Access
A machine learning and CFD based approach for fouling rapid prediction in shell-and-tube heat exchanger
Nuclear Engineering and Design·2024· 14 cited
Numerical modeling of alkali metal heat pipes
Annals of Nuclear Energy·2024· 8 cited
Numerical Simulation of Agglomeration Characteristics of Liquid Lead-Bismuth Eutectic (LBE) Impurity Particles
2024· 1 cited
Thermal-Hydraulic Analysis of the Upper Plenum in a Typical LFR During a Reactivity Insertion Accident
2024
Performance evaluation of accident tolerant Cr-coated Zr alloy cladding under accident conditions based on a refined degradation model
Progress in Nuclear Energy·2024· 11 cited
Safety analysis code development and validation for lead-cooled fast reactor with helical coiled once-through steam generator
Annals of Nuclear Energy·2024
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Frequent Co-authors

Suizheng Qiu(45), Wenxi Tian(38), Dalin Zhang(19), Yapei Zhang(11), Chenglong Wang(9), Ronghua Chen(7), Dong Wang(5), Shihao Wu(5), Dianqiang Jiang(4), Xinyu Li(4), Ruhao Zhong(4), Y.P. Zhang(4), Kailun Guo(4), Shibao Wang(3), Hao Qin(3), Yicong Lan(3), Jian Yu(3), Mingjun Wang(3), Yehong Liao(3), Zhenxun Peng(3)