JEONG, Jae Jun
- Major
- Nuclear Systems Major
- Lab
- Room 910 @ Mechanical Engineering Building
- Office
- 051-510-2455
- Website
- http://nsmsl.pusan.ac.kr/
- jjjeong@pusan.ac.kr
Research Field
- Development of multi-scale thermal-hydraulics analysis system
- System-scale, Component-scale, other scale
- Code model development such as one-dimensional optimum safety analysis code MARS, instrument analysis code CUPID
- Multi-physics code system for nuclear reactor analysis
- Analysis and optimal design research on core dynamics, nuclear fuel, structure, materials, water chemistry
- Multi-sector integrated reactor system analysis system construction
- Development of simulator and virtual reactor
- Realization of a virtual reactor by constructing input system of safety analysis code such as MARS and CUPID
- Study on reactor safety analysis through virtual reactor and simulator
- Simulation of critical accidents and study of thermal hydraulic phenomena
- Numerical solution method for multi-phase flows
- Numerical Study on Multiphase Flow
- Implementation of Multiphase Flow Modeling Code and Application Methodology of Numerical Analysis Method
Career
- 2011.03~Present : Nuclear Engineering Professor Pusan Nat'l Univ, Korea
- 2008.03~2011.02 : Advanced Nuclear System Eng. Adjunct Professor UST, Korea
- 2006.03~2007.02 : Nuclear Safety Visiting Scientist Purdue Univ., USA
- 1994.05~1995.04 : Nuclear Safety Visiting Scientist, CEA, Grenoble, France
- 1990.08~1999.08 : Nuclear Safety Senior Researcher KAERI, Korea