A5007953670- Nuclear Engineering Thermal-Hydraulics
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Heat Transfer and Boiling Studies
- Heat transfer and supercritical fluids
- Fluid Dynamics and Mixing
- Fluid Dynamics and Heat Transfer
- Computational Fluid Dynamics and Aerodynamics
- Combustion and Detonation Processes
- Fusion materials and technologies
- Risk and Safety Analysis
- Spacecraft and Cryogenic Technologies
- Metallurgical Processes and Thermodynamics
- Cyclone Separators and Fluid Dynamics
- Heat Transfer Mechanisms
- Metallurgy and Material Forming
- Wind and Air Flow Studies
- Nuclear and radioactivity studies
- Particle Dynamics in Fluid Flows
- Heat Transfer and Optimization
- Robotic Mechanisms and Dynamics
- Drilling and Well Engineering
- Marine and Coastal Research
- Graphite, nuclear technology, radiation studies
- Nuclear Physics and Applications
Seoul National University
2015-2024
Korea Institute of Nuclear Safety
2021
Argonne National Laboratory
2019
Korea Atomic Energy Research Institute
2007-2013
University of Tennessee at Knoxville
2006-2007
The CUPID code has been developed at KAERI for a transient, three-dimensional analysis of two-phase flow in light water nuclear reactor components. It can provide both component-scale and CFD-scale simulation by using porous media or an open model flow. In this paper, recent advances the are presented three sections. First, domain decomposition parallel method implemented is described with efficiency test multiple processors. Then, coupling CUPID-MARS via heat structure introduced, where...
Heat-pipe-cooled microreactors (HPRs) have advantages such as a compact design, easy transportation, and improved system reliability stability. The core of an HPR consists fuel rods heat pipes in monolith, which is solid block structure containing many holes for the pipes. When designing HPR, high thermal stress reactivity feedback owing to expansion are important considerations. Therefore, high-fidelity multiphysics analysis tool required accurately analyzing core. performing analysis, it...
Offshore nuclear power plants are characterized by a potential oscillatory motion depending on ocean waves. Investigating the local flow behavior in system undergoing oscillating is necessary. In particular, because void fraction near heating element surface significantly affects nucleating boiling heat transfer and critical flux, understanding dynamic of very important. Therefore, this study, as an essential first step predicting departure from nucleate offshore reactors, air–water bubbly...
A multiphysics analysis system for neutronics/thermomechanical/heat pipe thermal of heat pipe–cooled micro reactors was developed using the PRAGMA code as neutronics engine. PRAGMA, which a graphics processing unit (GPU)-based continuous-energy Monte Carlo power reactor applications, now has an extended geometry package to handle geometries with unstructured meshes generated by Coreform Cubit. The NVIDIA ray-tracing engine OptiX been exploited efficient neutron transport on mesh geometry. On...
Liquid film thickness measurements under temperature-varying conditions in a two-phase flow are of great importance to refining our understanding flows. In order overcome the limitations conventional electrical means measuring liquid film, this study proposes three-electrode conductance method, with device fabricated on flexible printed circuit board (FPCB). The method offers advantage applicability varying temperatures principle, while FPCB has usability curved surfaces and relatively...
Abstract There have been recent efforts to establish methods for high-fidelity and multi-physics simulation with coupled thermal–hydraulic (T/H) neutronics codes the entire core of a light water reactor under accident conditions. Considering computing power necessary pin-by-pin analysis core, subchannel-scale T/H is considered appropriate achieve acceptable accuracy in an optimal computational time. In present study, applicability in-house code CUPID Korea Atomic Energy Research...
In a nuclear reactor containment, wall condensation forms with noncondensable gases and their accumulation near the condensate film leads to significant reduction in heat transfer. framework of safety, presence is high relevance regards safety concerns as it closely associated peak pressure predictions for containment integrity performance components installed cooling accident conditions. present study, CUPID code, which has been developed by KAERI analysis transient two-phase flows...
Unlike land-based nuclear power plants, a marine or floating reactor is affected by external forces due to ocean conditions. These can cause additional accelerations and affect each system equipment of the reactor. Therefore, in designing evaluating its performance stability, thermal hydraulic safety analysis code necessary consider hydrodynamic effects ship motion. MARS, which code, includes dynamic motion model that simulate thermal-hydraulic phenomena under three-dimensional calculating...