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Wenxi Tian

Observed names: Tian Wenxi, Tian, Wenxi, W TIAN, W. X. Tian, W.-H. TIAN, W.X. Tian, Wen-Xi Tian, Wen-xi Tian, WenXi TIAN, WenXi Tian, Wenxi TIAN, wenxi Tian
Observed institutions: Harbin Engineering University, China Academy of Space Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Nuclear Power Institute of China, The University of Tokyo, Xi'an Jiaotong University
ORCID: 0000-0001-6815-6974
Observed ORCID: 0000-0001-6815-6974
OpenAlex ID: A5100626435
Recent progress of CFD applications in PWR thermal hydraulics study and future directions
2020 · Mingjun Wang, Yingjie Wang, et al. · Annals of Nuclear Energy · 263
Two-phase bubbly flow simulation using CFD method: A review of models for interfacial forces
2020 · Irfan Khan, Mingjun Wang, et al. · Progress in Nuclear Energy · 166
Review of Thermal-Hydraulic Issues and Studies of Lead-based fast reactors
2019 · Yan Zhang, Chenglong Wang, et al. · Renewable and Sustainable Energy Reviews · 147
Fluoride-salt-cooled high-temperature reactors: Review of historical milestones, research status, challenges, and outlook
2022 · Dianqiang Jiang, Dalin Zhang, et al. · Renewable and Sustainable Energy Reviews · 137
Effects of turbulence models on forced convection subcooled boiling in vertical pipe
2015 · Rui Zhang, Tenglong Cong, et al. · Annals of Nuclear Energy · 137
Applications of ANNs in flow and heat transfer problems in nuclear engineering: A review work
2012 · Tenglong Cong, Guanghui Su, et al. · Progress in Nuclear Energy · 131
Experimental study on heat pipe thermoelectric generator for industrial high temperature waste heat recovery
2020 · Chenglong Wang, Simiao Tang, et al. · Applied Thermal Engineering · 125
Study on the characteristics of the sodium heat pipe in passive residual heat removal system of molten salt reactor
2013 · Chenglong Wang, Dalin Zhang, et al. · Nuclear Engineering and Design · 97
Experimental evaluation on heat transfer limits of sodium heat pipe with screen mesh for nuclear reactor system
2022 · Zhixing Tian, Jiarui Zhang, et al. · Applied Thermal Engineering · 88
Experimental investigation on the heat transfer performance of high-temperature potassium heat pipe for nuclear reactor
2021 · Zhixing Tian, Xiao Liu, et al. · Nuclear Engineering and Design · 88
Isothermal experiments on steam oxidation of magnetron-sputtered chromium-coated zirconium alloy cladding at 1200 ℃
2022 · Dong Wang, Ruhao Zhong, et al. · Corrosion Science · 86
A Review on Analysis of LWR Severe Accident
2015 · Y. P. Zhang, S. P. Niu, et al. · Journal of Nuclear Engineering and Radiation Science · 86
Analysis of safety margin of in-vessel retention for AP1000
2010 · Y.P. Zhang, S.Z. Qiu, et al. · Nuclear Engineering and Design · 81
Numerical computation of thermally controlled steam bubble condensation using Moving Particle Semi-implicit (MPS) method
2009 · Wenxi Tian, Yuki Ishiwatari, et al. · Annals of Nuclear Energy · 80
Conceptual design and analysis of a multipurpose micro nuclear reactor power source
2018 · Hao Sun, Chenglong wang, et al. · Annals of Nuclear Energy · 79
A review of CFD studies on thermal hydraulic analysis of coolant flow through fuel rod bundles in nuclear reactor
2024 · Mingjun Wang, Haoran Ju, et al. · Progress in Nuclear Energy · 78
Numerical investigation on startup characteristics of high temperature heat pipe for nuclear reactor
2021 · Zeqin Zhang, Xiaoming Chai, et al. · Nuclear Engineering and Design · 78
Performance analysis of heat pipe radiator unit for space nuclear power reactor
2017 · Chenglong Wang, Jing Chen, et al. · Annals of Nuclear Energy · 77
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
2019 · Chenglong Wang, Hao Sun, et al. · Nuclear Engineering and Technology · 75
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Multi-objective optimization of helical coil steam generator in high temperature gas reactors with genetic algorithm and response surface method
2022 · Jinxiang Sun, Ruibo Zhang, et al. · Energy · 74
Natural convection heat transfer in corium pools: A review work of experimental studies
2014 · Luteng Zhang, Yukun Zhou, et al. · Progress in Nuclear Energy · 74
Thermal hydraulic phenomena related to small break LOCAs in AP1000
2011 · W.W. Wang, G.H. Su, et al. · Progress in Nuclear Energy · 74
CFD simulation of flow and heat transfer characteristics in a 5×5 fuel rod bundles with spacer grids of advanced PWR
2019 · Yingjie Wang, Mingjun Wang, et al. · Nuclear Engineering and Technology · 72
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Conceptual design and analysis of a megawatt power level heat pipe cooled space reactor power system
2020 · Wenwen Zhang, Dalin Zhang, et al. · Annals of Nuclear Energy · 70
Prediction of CHF in vertical heated tubes based on CFD methodology
2014 · Rui Zhang, Tenglong Cong, et al. · Progress in Nuclear Energy · 70
Works count: 1,033
Citation count: 15,080
H-index: 51
I10-index: 463
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