The physical phenomenon of the flow and heat transfer characteristic in vertical narrow annulus channel is a little different from general channel. It is valuable to improve the model veracity for exactly predicting the nuclear power system key physical phenomenon. The heat transfer characteristic of two narrow annulus channels (narrow gap 1.0mm and 1.5mm) is analyzed by means of the RELAPSCDAPSIM/MOD3.4 code recently developed by SDTP. Compared with related experiment data, the results show that the new developed code could predict key parameters such as fluid temperature, wall temperature, heat transfer coefficient, pressure drop, the occurrence condition of the flow instability and so on. The code has the ability to simulate the narrow annulus channel heat transfer characteristic.
- Nuclear Engineering Division
Evaluation of the Flow and Heat Transfer Characteristic in Vertical Narrow Annulus Channel Based on the RELAPSCDAPSIM/MOD3.4 Code
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Liu, J, & Peng, M. "Evaluation of the Flow and Heat Transfer Characteristic in Vertical Narrow Annulus Channel Based on the RELAPSCDAPSIM/MOD3.4 Code." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition. Brussels, Belgium. July 12–16, 2009. pp. 489-495. ASME. https://doi.org/10.1115/ICONE17-75452
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