Introduction

Professor

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JEONG, Jae Jun

Major
Nuclear Systems Major
Lab
Room 910 @ Mechanical Engineering Building
Office
051-510-2455
Website
http://nsmsl.pusan.ac.kr/ 
Email
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