A Semi-implicit Numerical Scheme for A Transient Two-Fluid Three-Field Model on An Unstructured Grid
International Communications in Heat and Mass Transfer, Vol.35, No.3, pp.597-605, 2008
Publications
A Semi-implicit Numerical Scheme for Transient Two-phase Flows on Unstructured Grids
Nuclear Engineering and Design, Vol.238, No.12, pp.3403-3412, 2008
An Unstructured SMAC Algorithm for Thermal Non-equilibrium Two-phase Flows
International Communications in Heat and Mass Transfer, Vol.36, No.1, pp.16-24, 2009
Numerical Effects of the Semi-conservative Form of Momentum Equations for Multi-dimensional Two-phase Flows
Nuclear Engineering and Design, Vol.239, No.11, pp.2365-2371, 2009
A Fast-running Semi-implicit Numerical Scheme for Transient Two-phase Flows on Unstructured Grids
Numerical Heat Transfer, Part B: Fundamentals, Vol.56, pp.432-454, 2009
Implementation of a Second-order Upwind Method in a Semi-implicit Two-phase Flow Code on Unstructured Meshes
Annals of Nuclear Energy, Vol.37, No.4, pp.606-614, 2010
Development and Preliminary Assessment of a Three-dimensional Thermal Hydraulics Code, CUPID
Nuclear Engineering Technology, Vol.42, No.3, pp.279-296, 2010
An Improved Numerical Scheme to Evaluate the Pressure Gradient on Unstructured Meshes for Two-phase Flow Analysis
International Communications in Heat and Mass Transfer, Vol.37, No.9, pp.1273-1279, 2010
Computational Analysis of Downcomer Boiling Phenomena Using a Component Thermal Hydraulic Analysis Code, CUPID
Journal of Engineering for Gas Turbines and Power, Vol.133, No.5, pp.250914, 2010
The CUPID Code Development and Assessment Strategy
Nuclear Engineering Technology, Vol.42, No.6, pp.636-656, 2010
A Continuity-Based Semi-implicit Scheme for Transient Two-Phase Flows
Journal of Nuclear Science and Technology, Vol.47, No.9, pp.779-789, 2012
Assessment of the Two-phase Flow Models in the CUPID Code Using the Downcomer Boiling Experiment
Journal of Nuclear Science and Technology, Vol.49, No.1, pp.78-89, 2012
Multi-scale Thermal-hydraulic Analysis of PWRs Using the CUPID Code,
Nuclear Engineering and Technology, Vol.44, No.8, pp.831-846, 2012
An Implicit Code Coupling of 1-D System Code and 3-D In-house CFD Code for Multi-scaled Simulations of Nuclear Reactor Transients
Annals of Nuclear Energy, Vol.59, pp.80-91, 2013
Numerical Study for CANDU Moderator Temperature Prediction by Using the Two-phase Flow Anaylsis Code, CUPID
Annals of Nuclear Energy, Vol.59, pp.139-148, 2013
Simulation of Single- and Two-phase Natural Circulation in the Passive Condensate Cooling Tank Using the CUPID Code
Journal of Nuclear Science and Technology, Vol.50, No.7, pp.709-722, 2013
A Multi-scale Analysis of the Transient Behavior of an Advanced Safety Injection Tank
Annals of Nuclear Energy, Vol.59, pp.80-91, 2013
Simulations of Air-Water Flow and Subcooled Boiling Flow Using the CUPID Code
Journal of Nuclear Science and Technology, Vol.50, No.8, pp.813-827, 2013
Assessment of the CUPID Code Applicability to the Thermal-hydraulic Analysis of a CANDU Moderator System
Progress in Nuclear Energy, Vol.75 pp.72-79, 2014
Heat Structure Coupling of CUPID and MARS for the Multi-scale Simulation of the Passive Auxiliary Feedwater System
Nuclear Engineering and Design, Vol.273, pp.459-468, 2014
Development of CUPID-SG for the Analysis of Two-phase Flows in PWR Steam Generators
Journal of Nuclear Science and Technology, Vol.50, No.8, pp.813-827, 2013
Recent Improvements in the CUPID Code for a Multi-dimensional Two-phase Flow Analysis of Nuclear Reactor Components
Nuclear Engineering Technology, Vol.46, No.5, pp.655-666, 2014
Nonorthogonality Correction Method for a Two-phase Semi-implicit Algorithm on a Polyhedral Unstructured Mesh
Numerical Heat Transfer, Part B, Vol.68, pp.387-402, 2015
Numerical Investigation of the CANDU Moderator Thermal-hydraulics Using the CUPID Code
Progress in Nuclear Energy, Vol.85 pp.541-547, 2015
Domain Decomposition Parallel Computing for Transient Two-phase Flow of Nuclear Reactors
Journal of Mechanical Science and Technology, VOl.30, No.5, pp.2045-2057, 2016
An Implicit Numerical Scheme for the Simulation of Three-dimensional Two-phase Flows in Light Water Nuclear Reactors
Numerical Heat Transfer, Part B, Vol.70, No.3, pp.183-199, 2016
Preliminary Study for a PWR Steam Generator with CUPID/MARS Multi-scale Thermal-hydraulics Simulation
Applied Thermal Engineering, Vol.115, pp.1245-1254, 2017
Comparative Study of the Two-fluid Momentum Equations for Multi-dimensional Bubbly Flows: Modification of Reynolds Stress,
Journal of Mechanical Science and Technology, Vol.31, No.1 pp.207-214, 2017
Assessment of the MARS Code Using the Two-phase Natural Circulation Experiments at a Core Catcher Test Facility
Science and Technology of Nuclear Installations, Vol.2017, ID.5731420, 2017
Improvement of the Two-fluid Momentum Equation Using a Modified Reynolds Stress Model for Horizontal Turbulent Bubbly Flows
Chemical Engineering Science, Vol.173 pp.208-217, 2017
Multi-physics Simulation of Nuclear Reactor Core by Coupled Simulation Using CUPID/MASTER
International Journal of Heat and Mass Transfer, Vol.115 pp.1020-1032, 2017
Numerical Approach to Siphon Break Phenomena in a Research Reactor Pool Using the CUPID Code
Nuclear Engineering and Design, VOl.326 pp.133-142, 2018