Kai Wang

ORCID: 0000-0002-9966-7002
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About
Contact & Profiles
Research Areas
  • Heat Transfer and Boiling Studies
  • Nuclear Engineering Thermal-Hydraulics
  • Heat Transfer and Optimization
  • Fluid Dynamics and Mixing
  • Fluid Dynamics and Heat Transfer
  • Nuclear reactor physics and engineering
  • Nuclear Materials and Properties
  • Heat Transfer Mechanisms
  • Metallurgical Processes and Thermodynamics
  • Heat transfer and supercritical fluids
  • Fluid Dynamics and Thin Films
  • Nuclear and radioactivity studies
  • Cyclone Separators and Fluid Dynamics
  • Optical measurement and interference techniques
  • Particle Dynamics in Fluid Flows
  • Surface Roughness and Optical Measurements
  • Fluid Dynamics Simulations and Interactions
  • Granular flow and fluidized beds
  • Advanced Control Systems Optimization
  • Thermochemical Biomass Conversion Processes
  • Neural Networks and Applications
  • Face recognition and analysis
  • Polymer Science and Applications
  • Optical Polarization and Ellipsometry
  • Environmental Changes in China

The University of Tokyo
2018-2024

Sun Yat-sen University
2022-2024

Key Laboratory of Nuclear Radiation and Nuclear Energy Technology
2024

China Huadian Corporation (China)
2022

Shanghai University of Electric Power
2021

Xi'an Jiaotong University
2016-2018

Kean University
2017

Grenoble Images Parole Signal Automatique
2013-2015

Huaibei Normal University
2009

10.1016/j.icheatmasstransfer.2025.108942 article EN International Communications in Heat and Mass Transfer 2025-04-15

10.1016/j.ijheatmasstransfer.2019.03.020 article EN International Journal of Heat and Mass Transfer 2019-03-09

10.1016/j.ijheatmasstransfer.2019.118966 article EN International Journal of Heat and Mass Transfer 2019-11-01

This study conducts a critical heat flux (CHF) experiment on carbon steel block, and the block is positioned slope that declined at angles of 5° 10°. The results were then analyzed compared with obtained from copper had been conducted previously same test facility. comparison showed several different types phenomena occurred, CHF both 10° was much lower than block. Detailed images heating surface each material acquired by high-speed camera under fluxes analyzed. generates more bubbles to...

10.1080/00223131.2018.1470945 article EN Journal of Nuclear Science and Technology 2018-05-18

10.1016/j.ijheatmasstransfer.2020.119866 article EN International Journal of Heat and Mass Transfer 2020-05-16

Due to the important role critical heat flux (CHF) plays in boiling field, it is of great significance study CHF, especially mechanism CHF nucleate boiling. In this study, a new model predict both pool and flow downward-face was proposed relationship between nucleation site density (NSD) studied. The based on bubble interaction theory, which assumed that happened due coalescing bubbles generated heating surface prevented liquid be supplied. NSD derived from previous observations experiments...

10.1080/00223131.2019.1644246 article EN Journal of Nuclear Science and Technology 2019-07-22

Facial landmarking locates the key facial feature points on data, which provides not only information semantic structures, but also prior knowledge for other types of analysis. However, most existing works still focus 2D image is quite sensitive to lighting condition changes. In order address this limitation, paper proposed a coarse-to-fine method based 3D scan data extracted from professional equipment automatically and accurately estimate landmark localization. Specifically, we firstly...

10.1142/s0219691318400076 article EN International Journal of Wavelets Multiresolution and Information Processing 2018-01-04

In this study, experiments of downward-facing flow boiling were conducted to investigate material effects on CHF. Experiments using aluminum, copper, and carbon steel. It was found that different materials had CHFs. Aluminum has the biggest CHF while copper lowest for each mass flux. After experiment, surface wettability increased became rougher, which probably due oxidation process during nucleate boiling. The difference is likely be related wettability, roughness thermal effusivity,...

10.1016/j.net.2021.03.024 article EN cc-by-nc-nd Nuclear Engineering and Technology 2021-04-02
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