Published October 2006
| Version v1
Journal article
Investigation of critical heat flux of annular flow in vertical upward round tube
Creators
- 1. Xi'an Jiaotong Univ., Xi'an (China). State Key Laboratory of Multiphase Flow in Power Engineering
- 2. Xi'an Jiaotong Univ., Xi'an (China). School of Energy and Power Engineering
Description
Prediction of Critical Heat Flux at high mass quality is important for the safety of once-through steam generator and the reactor core under accidental conditions. Based on the theory for droplet entrainment, droplet deposition and liquid film evaporation, the film thickness and film mass flow rate distribution along axis are calculated at vertical upward round tube. The dryout emerges at the point where the film is depleted due to the balance of entrainment, deposition and evaporation. The theoretical CHF values are higher than that of experimental data, with error within 30%. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 27
- Journal Issue
- 5
- Journal Page Range
- p. 42-47
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 38093561
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- ANNULAR SPACE; CRITICAL HEAT FLUX; DEPOSITION; DROPLETS; DRYOUT; ENTRAINMENT; EVAPORATION; FILM FLOW; FILMS; FLOW RATE; MASS; MATHEMATICAL MODELS; REACTOR SAFETY; SPATIAL DISTRIBUTION; THICKNESS; TUBES
- Descriptors DEC
- CONFIGURATION; DIMENSIONS; DISTRIBUTION; FLUID FLOW; HEAT FLUX; PARTICLES; PHASE TRANSFORMATIONS; SAFETY; SPACE
Optional Information
- Notes
- 9 figs., 8 refs.