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

Numerical analysis of thermal-hydraulic behavior of supercritical water in vertical upward/downward flow channels 1 corresp first-author Corresponding author. E-mail: guhanyang@stju.edu.cn Corresponding author. E-mail: guhanyang@stju.edu.cn guhanyang@stju.edu.cn 1 1 1 School of Nuclear Science and Engineering, Shanghai Jiaotong University, Shanghai 200240, China School of Nuclear Science and Engineering, Shanghai Jiaotong University, Shanghai 200240, China 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. Supercritical water reactor CFD Heat transfer References Oka Y , Koshizuka S , Design concept of once-through cycle supercritical pressure light water cooled reactors . In: Proceeding of SCR . Tokyo, Japan , November 6-8, 2000 , 1 - 22 . Design concept of once-through cycle supercritical pressure light water cooled reactors Yoo J , Ishiwatari Y , Oka Y , et al . Composite core design of high power density supercritical water cooled fast reactor. 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