抄録
In nuclear power plants, the capacity of heat transfer is related with flow characteristics in fuel channels. It is significant to choose the suitable turbulence model for analysis and calculating friction pressure drop across the fuel channel for understanding the system features and promoting system design. In this paper, computational fluid dynamics (CFD) method was used to calculate friction factor for CANDU-6 37-element bundle fuel channel. The calculation was carried out with four turbulence models which are standard k-ε model, SST model, SSG Reynolds Stress model and BSL Reynolds Stress model respectively in the range 3.0×10^4<Re<5.8×10^5. The results were compared with empirical correlations. It shows that the results of SST model have the best agreement among that of four models and that of k-ε model and BSL RS model take the second place. The flow friction is large in sub-channels between outer ring and intermediate ring of rods but there is no significant effect on results of friction factor calculated whether to solve out secondary flow on cross section or not. This paper provides the basis for solving complex thermal hydraulic problems using CFD method with appropriate turbulence model in the next study.
