1. Foundamental research on flow and heat transfer in new type of fuel element channels
    新型核动力换热元件热工水力基础特性理论与实验研究

2. Development of code on thermal-hydraulic and safety ananlysis of nuclear reactor
    反应堆热工水力与安全分析程序开发研究

3. Multidimensional-coupling numetical simulation using system, subchannel code and CFD softwares.       
    多尺度耦合(系统程序/子通道程序/三维CFD程序)的反应堆热工水力数值模拟研究

4. Application of advanced numerical method in nuclear thermalhydraulics field
    先进数值方法(MPS，MOC，VOF)在核反应堆热工水力领域的应用研究

5. Coupling analysis of neutronics and thermalhydraulics
    中子物理-热工水力耦合研究

6. Design, safety evalution and optimization of advanced reactors(AP,SCWR,MSR,SFR etc..)     
   先进堆堆芯设计、安全评价及优化研究