Published 1990
| Version v1
Miscellaneous
Development of a model to predict CHF enhancement in subchannels with spacing devices
Creators
- 1. Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.
Description
An enhancement factor correlation was developed to improve the prediction of CHF at different axial locations in a fuel bundle by accounting for the effect of quality, mass flux and bundle-appendage enhancement. The correlation was developed with CHF data from an experiment with a test section comprised of three equal subchannels. It adequately accounts for the effect of spacers, mass flux and local quality in predicting the CHF enhancement for upstream dryouts. Additional work is suggested to further improve the correlation's predictive capability, especially in subchannels, where misalignment affects the dryout enhancement. (Author) 11 refs., 3 figs
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 11th Annual Conference of the Canadian Nuclear Society
- Imprint Pagination
- 440 p.
- Journal Page Range
- p. 12.9-12.11.
- Report number
- INIS-mf--13847
Conference
- Title
- Canadian Nuclear Society 11. annual conference.
- Dates
- 3-6 Jun 1990.
- Place
- Toronto, ON (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 25031367
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; CRITICAL HEAT FLUX; DRYOUT; FLUID FLOW; FORECASTING; FUEL ELEMENT CLUSTERS
- Descriptors DEC
- FUEL ASSEMBLIES; HEAT FLUX; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS