A5040952064- Nuclear Engineering Thermal-Hydraulics
- Risk and Safety Analysis
- Combustion and Detonation Processes
- Nuclear reactor physics and engineering
- Marine and Coastal Research
- Nuclear Materials and Properties
- Education, Safety, and Science Studies
Korea Institute of Nuclear Safety
2023-2024
Steam line break accident (SLB) in the nuclear reactor is one of representative Non-LOCA accidents which thermal-hydraulics and neutron kinetics are strongly coupled each other. Thus, multi-scale multi-physics approach applied this study order to examine a realistic safety margin. An entire coolant system modelled by scale node, whereas sub-channel resolution for region interest such as core. Fuel performance code extended consider full core pin-wise fuel behaviour. The MARU platform...
Considering that system analysis codes are used for the evaluation of performance Passive Safety Systems (PSSs), it is important to investigate capability code reliably predict heat transfer and natural circulation flow, which main phenomena governing a PSS. Since MARS-KS has been widely validated models, this study focuses on evaluating its single two-phase pressure drops flow. The straight pipe simulation results indicate drop predictions reliable within ±5 % error margin single-phase flow...
In this study, the effect of performance issues on Passive Emergency Core Cooling System (PECCS), a type Safety (PSS), was evaluated. The PECCS relies natural phenomena such as gravity, density difference, and pressure difference to operating. Its driving force is lower compared that active safety system, making it necessary evaluate its in various transient situations. Therefore, there are concerns about whether PSS can sufficiently perform functions Major were identified through evaluation...