Abstract

Diameter effect on heat transfer deterioration (HTD) was numerically studied for supercritical water flowing upward in circular tubes and annular channels at high heat flux and low mass flux based on validated turbulence model. When the same boundary conditions were applied, i.e. heat flux, mass flux, and inlet temperature, it was found that in circular tubes the first wall temperature peak moves upstream and the magnitude of the peak increases first and then decreases with the increase of tube diameter, the second peak moves downstream with the increase of tube diameter. Whereas in annular channels with a fixed inner diameter, HTD is suppressed when the outer diameter is small and HTD occurs gradually with the increase of outer diameter. These phenomena are consistent with previous experimental results. The mechanism was analyzed based on fully developed turbulent velocity profile at the inlet of the heated sections. Increasing inner diameter for circular tubes or outer diameter for annular channels will result in the decrease of maximum velocity and velocity gradient in the near wall region, which makes velocity profile in this region much easier to be flattened by the buoyancy. Then an M-shaped velocity profile is formed, which will significantly decrease the Reynolds shear stress and turbulent kinetic energy and hence impair the heat transfer and cause HTD. For the same flow conditions, HTD is much easier to occur in circular tubes than in annular channels with the same hydraulic diameters.

Highlights

  • The supercritical water reactor (SCWR) is one of the six generation IV nuclear systems

  • Diameter Effect in Circular Tubes In Cheng et al.’s recent work (Cheng et al, 2017), two peaks of wall temperature were found in the simulation results of mixed convective heat transfer at the same flow condition corresponding to Case C2 in the present study when heat transfer deterioration (HTD) occurred, which was consistent with Shitsman’s experimental results

  • The wall temperature distribution in the axial direction is shown in Figure 5 and the mechanism was explained in detail with axial velocity profiles and turbulent kinetic energy (TKE) distributions in radial direction

Read more

Summary

Introduction

The supercritical water reactor (SCWR) is one of the six generation IV nuclear systems. One advantage of SCWR is to increase the nuclear power plants thermal efficiency, which is about 36–38%, to about 45–50% (Pioro and Mokry, 2011). Because no phase change occurs for supercritical water, SCWR can reduce the capital and operational costs through eliminating steam related facilities (Cheng et al, 2003; Pioro and Duffey, 2005). Pioro and Mokry (2011) provided the pressure-temperature diagram of water (Figure 1). The critical temperature and critical pressure of water are 373.95 and 22.06 MPa, respectively.

Objectives
Results
Conclusion
Full Text
Paper version not known

Talk to us

Join us for a 30 min session where you can share your feedback and ask us any queries you have

Schedule a call