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Wenbin Zhuo
Observed names:
W ZHUO,
W.B. Zhuo,
Wenbin ZHUO
Institution:
Nuclear Power Institute of China
Observed institutions:
China National Nuclear Corporation,
Nuclear Power Institute of China
OpenAlex ID:
A5039628169
Fluoride-Salt-cooled high-Temperature Advanced Reactor (FuSTAR): An integrated nuclear-based energy production and conversion system
2023
·
Dalin Zhang
, Xinyu Li
, et al.
·
Energy
·
46
Experimental evaluation of safety performance of emergency passive residual heat removal system in HPR1000
2017
·
D.C. Sun
, Y. Li
, et al.
·
Nuclear Engineering and Design
·
46
Experimental investigation on natural circulation characteristics of emergency passive residual heat removal system in HPR1000
2017
·
D.C. Sun
, Z. Xi
, et al.
·
Progress in Nuclear Energy
·
22
Upward two-phase flow patterns in vertical circular pipe under rolling condition
2020
·
Tianzhou Xie
, Jianjun Xu
, et al.
·
Progress in Nuclear Energy
·
14
Experimental investigation on repeatability of CHF in rod bundle with non-uniform axial heat flux distribution
2016
·
Shengjie Qin
, Xuemei Lang
, et al.
·
Progress in Nuclear Energy
·
14
Experimental study of the depressurization phenomena of supercritical carbon dioxide system
2023
·
Minyun Liu
, Yanping Huang
, et al.
·
Progress in Nuclear Energy
·
12
The development and verification of thermal-hydraulic code on passive residual heat removal system of Chinese advanced PWR
2006
·
Z XIAO
, S QIU
, et al.
·
Nuclear Science and Techniques
·
12
Experimental investigation on steam contact condensation in emergency makeup tank
2021
·
Y. Li
, D.L. Zhang
, et al.
·
Nuclear Engineering and Design
·
7
Dry-out characteristics of debris bed under different water injection conditions
2023
·
Yu Fang
, Houjun Gong
, et al.
·
Progress in Nuclear Energy
·
5
Experimental investigation of thermal–hydraulic parameters on the performance of a once-through steam generator (OTSG)
2025
·
Daiquan Du
, Ting Zhang
, et al.
·
Nuclear Engineering and Design
·
4
Analysis of the Brayton cycle coupled with a small fluoride salt-cooled high-temperature reactor
2023
·
Xiuting Liu
, Yanping Huang
, et al.
·
Frontiers in Energy Research
·
4
PDF
Experimental study on water injection and stratified steam explosion at the top of metal molten pool
2022
·
Shengxing Yang
, Houjun Gong
, et al.
·
Annals of Nuclear Energy
·
3
System-level experiments on depressurization transients in an S-CO2 nuclear power test loop: Effects of break location, break size, and containment backpressure
2026
·
Ruohan Zheng
, Yangle Wang
, et al.
·
Nuclear Engineering and Design
·
1
Numerical study on the liquid phase structural evolution of high-temperature metal-oxide mixture in the magnetic field
2025
·
Kerong Guo
, Houjun Gong
, et al.
·
International Journal of Thermal Sciences
·
1
Fluoride-Salt-Cooled High-Temperature Reactor: An Integrated Nuclear-Based Energy Production and Conversion System
2023
·
Dalin Zhang
, Xinyu Li
, et al.
·
SSRN Electronic Journal
·
1
Experimental Research of Flow Distribution at Reactor Core Inlet of ACP100
2022
·
Lei Ding
, Lin Jiang
, et al.
·
Frontiers in Energy Research
·
1
PDF
Experimental Study on Critical Flow of High-Temperature and High-Pressure Supercritical Carbon Dioxide at Transient State
2025
·
Ruohan Zheng
, Yanping Huang
, et al.
·
Green energy and technology
Fluoride-Salt-Cooled High-Temperature Reactor: An Integrated Nuclear-Based Energy Production and Conversion System
2023
·
Dalin Zhang
, Xinyu Li
, et al.
·
SSRN Electronic Journal
Experimental Research on Characteristics of Passive Residual Heat Removal System for Small Modular Reactors Under the Station Blackout Accident
2016
·
Xiaodong Lu
, Chuanxin Peng
, et al.
·
The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Thermal Hydraulic Facility for Full Length Bundle CHF Experiment
2014
·
Shengjie Qin
, Xuemei Lang
, et al.
·
The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Analysis of the Velocity Field of Thermal Stratification in Pipes
2013
·
Limiao Xing
, Wenbin Zhuo
, et al.
·
The Proceedings of the International Conference on Nuclear Engineering (ICONE)
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Works count:
21
Citation count:
193
H-index:
7
I10-index:
7
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