Published April 2001 | Version v1
Journal article

Three dimensional numerical simulation of sodium flow on small water leak in steam generator of fast reactor

  • 1. Tsinghua Univ., Beijing (China). Dept. of Thermal Engineering

Description

In order to calculate the sodium-water reaction products transport and diffusion in occurrence of small water leak in steam generator, a three dimensional numerical model of sodium steady flow in steam generator of fast reactors is established. The numerical model uses the distributed resistance along with volumetric porosity and surface permeability to model the effect of tubes on sodium flow in the steam generator. The distributed resistance of banks of tubes is correlated by the pressure drop formula of the flow perpendicular to tubes and the flow parallel to the tubes. Turbulence effects are modeled using a κ-ε model. Shell and support plate walls are modeled using the wall function approach. Good agreement is obtained between the computed results and experiments

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
22
Journal Issue
2
Journal Page Range
p. 150-154
ISSN
0258-0926