Numerical analysis of thermal-hydraulic behavior of supercritical water in vertical upward/downward flow channels
Creators
- 1. School of Nuclear Science and Engineering, Shanghai Jiaotong Univ., Shanghai (China)
Description
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. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Science and Techniques
- Journal Volume
- 19
- Journal Issue
- 3
- Journal Page Range
- p. 178-186
- ISSN
- 1001-8042
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 41120620
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- COMMUNITIES; FLUIDS; FUEL ASSEMBLIES; HEAT TRANSFER; HOT CHANNEL; MIXING; NUMERICAL ANALYSIS; SUPERCRITICAL STATE; THERMAL HYDRAULICS; TURBULENCE; WATER; WATER COOLED REACTORS
- Descriptors DEC
- ENERGY TRANSFER; FLUID MECHANICS; HYDRAULICS; HYDROGEN COMPOUNDS; MATHEMATICS; MECHANICS; OXYGEN COMPOUNDS; REACTORS
Optional Information
- Notes
- 9 figs., 1 tab., 29 refs.