Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2008, Vol. 19 ›› Issue (3): 178 doi: 10.1016/S1001-8042(08)60047-0

• MISCELLANEOUS • Previous Articles     Next Articles

Numerical analysis of thermal-hydraulic behavior of supercritical water in vertical upward/downward flow channels

GU Hanyang* YU Yiqi CHENG Xu LIU Xiaojing   

  1. School of Nuclear Science and Engineering, Shanghai Jiaotong University, Shanghai 200240, China
PDF ShareIt Export Citation
GU Hanyang YU Yiqi CHENG Xu LIU Xiaojing . Numerical analysis of thermal-hydraulic behavior of supercritical water in vertical upward/downward flow channels.Nuclear Science and Techniques, 2008, 19(3): 178     doi: 10.1016/S1001-8042(08)60047-0

Abstract: Investigations on the thermal-hydraulic behavior in the SCWR fuel assembly have obtained a significant attention in the international SCWR community. However, there is still a lack of understanding of the heat transfer behavior of supercritical fluids. In this paper, the numerical analysis is carried out to study the thermal-hydraulic behaviour in vertical sub-channels cooled by supercritical water. Remarkable differences in characteristics of secondary flow are found, especially in square lattice, between the upward flow and downward flow. The turbulence mixing across sub-channel gap for downward flow is much stronger than that for upward flow in wide lattice when the bulk temperature is lower than pseudo-critical point temperature. For downward flow, heat transfer deterioration phenomenon is suppressed with respect to the case of upward flow at the same conditions.

Key words: Supercritical water reactor, CFD, Heat transfer