Development and Validation of Multiscale Coupled Thermal-Hydraulic Code Combining RELAP5 and Fluent Code

In nuclear reactor system research, the multiscale coupled thermal-hydraulic (T-H) code and CFD is one of most prevalent research areas, it could help improve simulation fidelity optimize design. Additionally, a new idea known as function fitting method (FFM) for coupling parameter distribution has been newly proposed exchanging data on interface, which uses math equations to present velocity characteristics at interface. This error numerical instability. To verify validate abovementioned FFM, comparison between shape by FFM real was completed. Besides, Edwards pipe blowdown test results were used code. The showed good agreement with experiment results, better accuracy compared previous work. current work will establish ability explore operation permit precise local distribution.