Shixian Wang

ORCID: 0009-0009-1119-3809
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About
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Research Areas
  • Nuclear Engineering Thermal-Hydraulics
  • Heat Transfer and Boiling Studies
  • Fluid Dynamics and Mixing
  • Nuclear Materials and Properties
  • Nuclear reactor physics and engineering
  • Heat Transfer and Optimization
  • Particle Dynamics in Fluid Flows
  • Fluid Dynamics and Turbulent Flows
  • Computational Fluid Dynamics and Aerodynamics
  • Neural Networks and Applications
  • Phase Equilibria and Thermodynamics
  • Cyclone Separators and Fluid Dynamics
  • Aerodynamics and Acoustics in Jet Flows
  • Heat transfer and supercritical fluids

The University of Tokyo
2024

Northwestern Polytechnical University
2023

Sun Yat-sen University
2017

Abstract Our research thoroughly examines the Critical Heat Flux (CHF) in downward-facing flow boiling, essential for comprehending intricacy of CHF phenomenon. Conducted on a copper surface within loop, our uncovered significant differences between upstream and downstream regions, with predominantly occurring first. High-speed camera analysis during boiling crisis led to identification ‘CHF front,’ marking transition from nucleate film phases. This front typically originates progresses...

10.1115/icone31-124786 article EN Volume 15: Student Paper Competition 2024-08-04

Studies on debris bed formation behavior are of crucial importance for the improved evaluation core relocation and coolability that might be encountered in a Core Disruptive Accident (CDA) Sodium-cooled Fast Reactors (SFR). Motivated to clarify characteristics flow regimes underlying this behavior, both experimental investigations empirical-model development being performed at Sun Yat-sen University. As study, several series simulated experiments conducted by discharging various solid...

10.1115/icone25-66143 article EN 2017-07-02

This research paper presents a comprehensive examination of boiling dynamics, particularly near and at the Critical Heat Flux (CHF) level, using downward-facing flow experimental setup on copper surface. The study measured both CHF transient heat flux Departure from Nucleate Boiling (DNB) point in upstream (US) downstream (DS) regions. A significant finding was introduction front concept, acting as an interface between nucleate film phases. motion highlighted distinct behaviors US DS...

10.2139/ssrn.4646539 preprint EN 2023-01-01
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