Kin Wing Wong

Kin Wing Wong
KTH Royal Institute of Technology | KTH · Division of Nuclear Engineering

Master of Science

About

14
Publications
1,218
Reads
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50
Citations
Introduction
My Ph.D. topic is related to modeling the flow accelerated corrosion and erosion (FACE) problem in liquid heavy metals using computational fluid dynamics (CFD). This project aims to develop and validate modeling techniques for understanding flow-accelerated corrosion and erosion (FACE) processes in heavy liquid metal-cooled (HLM) reactors. The research is part of the SUNRISE (Sustainable Nuclear Energy Research In Sweden) project
Additional affiliations
December 2019 - February 2022
Gesellschaft für Anlagen und Reaktorsicherheit
Position
  • Wissenschaftlicher Mitarbeiter
October 2018 - August 2019
Paul Scherrer Institut
Position
  • Master's Student
July 2018 - October 2018
Kernkraftwerk Gösgen
Position
  • Safety Analysis Intern
Education
September 2017 - August 2019
École Polytechnique Fédérale de Lausanne
Field of study
  • Nuclear Engineering
September 2013 - July 2017
City University of Hong Kong
Field of study
  • Nuclear and Risk Engineering

Publications

Publications (14)
Conference Paper
This study investigates near-wall diffusive flux modeling for passive scalar transport in turbulent flows with high Schmidt (Sc) or Prandtl (Pr) numbers. Under these conditions, the diffusion boundary layer becomes significantly thinner than the velocity boundary layer. Capturing the concentration boundary layer presents challenges due to additiona...
Conference Paper
The SEFACE facility, specifically designed to study material damage caused by turbulent flow, utilizes a rotating disc configuration. We conducted a large-eddy simulation (LES) to examine the dynamics of turbulence near the rotating disk, which operates at high linear Reynolds numbers between 1 and 10 million. The Wall-Modelled LES feature in ANSYS...
Conference Paper
This paper proposes an empirical correction to the eddy-viscosity-based wall model for passive scalars, utilizing a two-layer concept to address variability caused by the low-pass filtering phenomenon in turbulent flows with high Schmidt (Sc) and Prandtl (Pr) numbers. The model incorporates two von Kármán-like constants ($k_{Re}$ and $k_{Sc}$) to d...
Article
Full-text available
Flow-accelerated corrosion and erosion (FACE) phenomena can be crucial for performance of structural elements in heavy liquid metal (HLM) cooled reactor systems. Existing experimental observations indicate that turbulent flow characteristic can affect FACE, but there is no quantitative data that can be used for model development and validation. Mai...
Conference Paper
Long-term material compatibility in heavy liquid metal (HLM) remains a challenge for the successful deployment of HLM-based technologies. Flow-accelerated corrosion and erosion (FACE) phenomena can lead to continual material deterioration, which needs to be considered throughout the reactor design stage. Nonetheless, known experimental data are ina...
Conference Paper
Full-text available
Measurement of the velocity field in thermal-hydraulic experiments is of great importance for phenomena interpretation and code validation. Direct measurement by means of Particle Image Velocimetry (PIV) is challenging in some multiphase's tests where the measurement system would be strongly affected by the phase interaction. A typical example can...
Conference Paper
Abstract – To meet the highest targets of sustainable energy generation, safety and reliability, life cycle cost, waste minimization and management, the Generation IV nuclear energy systems are being developed. The Lead cooled fast reactors (LFR’s) is a technology benefits from high boiling point of the coolant, its low vapor pressure, thermodynami...
Book
Das vom BMWi geförderte Projekt RS1565 zur Weiterentwicklung des AC² Thermohydraulik-Moduls ATHLET zur Simulation komplexer, zweiphasiger Strömungsphänomene hatte die Entwicklung und Ertüchtigung von Modellen und Methoden zum Ziel, um den zahlreichen nationalen und internationalen Nutzern von ATHLET ein leistungsstarkes und zuverlässiges Werkzeug f...
Technical Report
Full-text available
This User's Manual has been prepared to assist users in the effective application of the ATHLET computer code. ATHLET is an advanced best‐estimate system code which has been initially developed for the simulation of design basis and beyond design basis accidents (without core degradation) in light water reactors, including VVER and RBMK reactors. F...
Article
Helium gases are utilized to remove fission products from the molten salt fast reactor (MSFR) core during operation. Helium gases and other volatile fission products may be introduced into the intermediate heat exchanger channels. The effect of these gases on heat transfer is essential for the MSFR to operate properly, especially in laminar flow re...
Conference Paper
In the Molten Salt Fast Reactor (MSFR), helium gases are used to assist the extraction of fission products from the MSR core during operation. These helium gases and other volatile fission products can enter into the intermediate heat exchanger channels. Its effect on heat transfer is paramount to the operation of MSFR, especially for the laminar f...
Article
The occurrence of heat transfer deterioration (HTD) in supercritical pressure boilers, where the wall temperature rises abruptly is an undesirable phenomenon that is limiting the design of new promising engineering applications. This may cause operational problems such as tube burnouts which could result in a catastrophic system failure. Understand...
Conference Paper
Full-text available
With the concurrence of the loss of flow (LOFW) and loss of heat sink (LOHS) accident in the pool type Molten Salt Reactor (MSR), the boiling of the molten salt liquid could occur naturally due to the presence of the volumetric decay heat source inside the salt. To investigate the phase change phenomenon within the MSR channel during the accident,...
Conference Paper
With the advantages of the thermophysical property of supercritical carbon dioxide (SCO2), SCO2 has been proposed for being used as the coolant of the secondary system in a nuclear reactor to promote a higher thermal efficiency. However, heat transfer deterioration (HTD) in supercritical fluid became a potential operational problem for the supercri...

Questions

Question (1)
Question
What is the current temperature limit for a Superhydrophobic Surfaces? Can it be stable up to around 500 to 600 DegC?

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