Published December 2011
| Version v1
Journal article
Theoretical study on critical heat flux for reactor lower head using subscale boundary layer boiling model
Creators
- 1. Department of Nuclear Science and Technology, Xi'an Jiaotong University (China)
Description
Based on the subscale boundary layer model, a preliminary boundary layer thickness analysis is performed, which is treated with the conservation equation, in order to calculate the CHF. Predictive results of CHF are obtained by selecting the largest entrainment coefficient. The angle, which implicates the change beginning of the two-phase boundary layer thickness, will increase with the increasing radius. The result of CHF increases observably with the angle, and the maximum value appears in 90 degrees. Comparing the predictive results with the experimental data, a better result of CHF prediction is obtained with the improved subscale boundary layer model. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 32
- Journal Issue
- 6
- Journal Page Range
- p. 61-65
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 45102723
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- AFTER-HEAT; BOILING; BOUNDARY LAYERS; COMPARATIVE EVALUATIONS; CORIUM; CRITICAL HEAT FLUX; ENTRAINMENT; EQUATIONS; EXPERIMENTAL DATA; HEAD; PWR TYPE REACTORS; REACTOR VESSELS; THICKNESS
- Descriptors DEC
- BODY; CONTAINERS; DATA; DIMENSIONS; ENRICHED URANIUM REACTORS; EVALUATION; HEAT FLUX; INFORMATION; LAYERS; NUMERICAL DATA; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 figs., 9 refs.