About this Research Topic
High fidelity nuclear reactor thermal hydraulic simulations are a hot research topic in the development of nuclear engineering technology. The three-dimensional Computational Fluid Dynamics (CFD) and Computational Multi-phase Fluid Dynamics (CMFD) methods have attracted significant attention in predicting single-phase and multi-phase flows under steady-state or transient scenarios in the field of nuclear reactor engineering. Compared with three-dimensional thermal hydraulic methods, the traditional one-dimensional system analysis method contains inherent defects in the required accuracy and spatial resolution for a number of important nuclear reactor thermal-hydraulic phenomena.
At present the CFD method has been widely adopted in the nuclear industry, across both light water reactors and liquid metal cooled fast reactors, providing an effective solution for complex issues of thermal hydraulic analysis. However, the CFD method employs empirical models for turbulence simulation, heat transfer, multi-phase interaction and chemical reactions. Such models must be validated before they can be used with confidence in nuclear reactor applications. In addition, user practice guidelines play a critical role in achieving reliable results from CFD simulations.
This Research Topic will provide the necessary comprehensive coverage of CFDs, including application, development, current status and challenges. It aims to publish the most advanced and latest CFD research from around the world, applied to the simulation of issues affecting the safety of nuclear systems. Themes of interest include, but are not limited to:
1. CFD single phase simulation
2. CMFD simulation
3. Multi-scale coupling with CFD
4. Multi-physics coupling with CFD
5. Open source CFD code development and application
6. LES and DNS
7. Best Practice Guidelines (BPGs) research
8. Porous medium model application
9. Key components simulation using CFD method
10. Other applications of CFD in nuclear engineering
At present the CFD method has been widely adopted in the nuclear industry, across both light water reactors and liquid metal cooled fast reactors, providing an effective solution for complex issues of thermal hydraulic analysis. However, the CFD method employs empirical models for turbulence simulation, heat transfer, multi-phase interaction and chemical reactions. Such models must be validated before they can be used with confidence in nuclear reactor applications. In addition, user practice guidelines play a critical role in achieving reliable results from CFD simulations.
This Research Topic will provide the necessary comprehensive coverage of CFDs, including application, development, current status and challenges. It aims to publish the most advanced and latest CFD research from around the world, applied to the simulation of issues affecting the safety of nuclear systems. Themes of interest include, but are not limited to:
1. CFD single phase simulation
2. CMFD simulation
3. Multi-scale coupling with CFD
4. Multi-physics coupling with CFD
5. Open source CFD code development and application
6. LES and DNS
7. Best Practice Guidelines (BPGs) research
8. Porous medium model application
9. Key components simulation using CFD method
10. Other applications of CFD in nuclear engineering
Keywords: CFD, nuclear reactor, thermal-hydraulics, two-phase flow, high-fidelity simulation
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