کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
1728127 | 1521126 | 2014 | 10 صفحه PDF | دانلود رایگان |

• It is important to study thermal-hydraulic characteristics in a PBR for a HTGR.
• A CFD model is proposed to simulate flow and heat transfer in a segment of pebbles.
• Area and point contact treatments for adjacent pebbles are adopted in this study.
• Predicted dependences of Nu and friction factor agree with the correlations.
A high temperature gas cooled reactor (HTGR) with a pebble bed core (PBR) can be considered as one of the possible energy generation sources in the incoming future due to its inherently safe performance, lower power density, and higher conversion efficiency, etc. It is important to study the thermal-hydraulic characteristics in a PBR for optimum design and safe operation of a HTGR. In this paper, a computational fluid dynamics (CFD) methodology is proposed to investigate the thermal-hydraulic behavior in a segment of pebbles representing the central region of a PBR. Two kinds of contact modeling between adjacent pebbles are adopted, namely area and point contact treatments. The former contact treatment is a geometric approximation modeling. Based on the comparisons of thermal-hydraulic characteristics in the pebbles predicted by both contact treatments, no significant difference is revealed except for the near-wall secondary flow pattern. In addition, compared with the calculated results from the well-known correlations, the present predicted dependence of Nu number and friction factor on the particle Reynolds number shows good agreement qualitatively and quantitatively.
Journal: Annals of Nuclear Energy - Volume 72, October 2014, Pages 156–165