A5102006774- Nuclear Engineering Thermal-Hydraulics
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Heat Transfer and Boiling Studies
- Nuclear and radioactivity studies
- Risk and Safety Analysis
- Engineering Applied Research
- Geotechnical Engineering and Underground Structures
- Heat transfer and supercritical fluids
- Fluid Dynamics and Mixing
- Combustion and Detonation Processes
- Metallurgical Processes and Thermodynamics
- Seismic Waves and Analysis
- Vibration and Dynamic Analysis
- Seismic Imaging and Inversion Techniques
- Marine and Coastal Research
- Flow Measurement and Analysis
- Landslides and related hazards
- Agriculture, Soil, Plant Science
- Soil and Unsaturated Flow
- Elasticity and Material Modeling
- Seismic Performance and Analysis
- Simulation Techniques and Applications
- Earthquake and Tsunami Effects
- Education, Safety, and Science Studies
Seoul National University
2000-2013
The Ohio State University
1987-1990
This study investigates Equivalent Spherical Diameter (ESD) estimation at high inlet velocity pool scrubbing conditions using the Interfacial Area Transport Equation (IATE) diameter model including bubble-induced turbulence and interphase modeling. The compatibility of area-averaged Sauter Mean (SMD), Local (LED) void-weighted LED approaches to estimate ESD are explored proposed is validated against available experimental data. reveals that prevalent constant assumption in codes not...
Abstract Variational principles governing dynamics of fluid‐saturated linear elastic porous media are derived. Complementary as well direct formulations discussed. Discontinuities in the field variables, approximation space and excitation allowed for. Extensions variational to relax smootheness requirements on certain variables introduced along with some specizalizations convenient for finite element applications.
Abstract Garg's approximate analytical solutions of Biot's equations for wave propagation in a fluid‐saturated elastic porous solid infinite extent subjected to velocity boundary condition Heaviside function at one end are examined small and large drag. approximations were apparently introduced facilitate exact inversion Laplace transforms certain quantities. The compared with carefully evaluated numerical inverses the transform different soils widely varying properties. It is seen that most...
A horizontal U-shaped heat exchanger (HX) submerged in a pool is under development as piece of key equipment for passive safety system nuclear power plant (NPP). For the successful design HX and analysis NPP, reliable prediction transfer performance important. At present, systems are performed mainly using best-estimate thermal-hydraulic codes such RELAP5 MARS. However, those do not have suitable models both condensation tube natural convective nucleate boiling on tube, which ultimately...
This paper discusses a thermal-hydraulic analysis methodology using RETRAN-3D and assembles system analyses for pressurized thermal shock resulting from steam generator tube rupture accident in Kori Nuclear Unit 1. Through systematic definition of sequences RETRAN-3D, the most important parameters on downcomer overcooling were identified. The break location that leads to significant was found be hot leg side loop does not contain charging flow inlet. initial power level had large effect...
A thermal-hydraulic analysis methodology is established for a pressurized thermal shock (PTS) of the Kori Nuclear Unit-1 (KNU-1) power plant using RETRAN-3D. The effects important parameters on PTS are evaluated, such as initial level, break size, isolation depressurized steam generator (SG), and charging flow runback. As result, most dominant factors revealed level rate. Auxiliary feedwater (AFW) to SG should be isolated by operator action soon possible minimize flow. To mitigate risk...