1. Foundamental research on flow and heat transfer in new type of fuel element channels 

2. Development of code on thermal-hydraulic and safety analysis of nuclear reactor

3. Multidimensional-coupling numetical analysis using system code, subchannel code and CFD softwares.

4. Application of advanced numerical method in nuclear thermalhydraulics field

5. Coupling analysis of neutronics and thermalhydraulics

6. Design, safety evalution and optimization of advanced reactors(AP,SCWR,MSR,SFR etc..)