Published 1993
| Version v1
Miscellaneous
A generalized critical heat flux correlation for CANDU fuel geometries
Creators
- 1. Ontario Hydro, Toronto, ON (Canada)
- 2. IDEA Research International, Etobicoke, ON (Canada)
Description
A generalized non-dimensional critical heat flux correlation is developed. The correlation can be applied for any coolant, geometry, orientation and uniform or non-uniform axial, circumferential or radial flux profiles. The correlation is also applicable for subcooled and quality conditions. The correlation agrees very well with various available critical heat flux data. It is used to predict the critical channel power for Bruce NGS (Nuclear Generating Station) A and Pickering NGS A using various flux shapes. In most cases, the developed correlation results in larger critical channel powers than those predicted using 37-element flux corrected correlation and 28-element local conditions correlation. 28 refs., 9 figs., 3 tabs., 1 appendix
Additional details
Publishing Information
- ISBN
- 0-919784-31-3
- Imprint Title
- Canadian Nuclear Society/American Nuclear Society 4. international conference on simulation methods in nuclear engineering
- Imprint Pagination
- 2 v.
- Journal Page Range
- (v.1) [23 p.].
- Report number
- INIS-mf--14622
Conference
- Title
- 4. international conference on simulation methods in nuclear engineering.
- Dates
- 2-4 Jun 1993.
- Place
- Montreal, PQ (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 26073937
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; CORRELATIONS; CRITICAL HEAT FLUX; DRYOUT; FUEL CHANNELS; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; POWER; REACTOR SAFETY
- Descriptors DEC
- ENERGY TRANSFER; FUEL ASSEMBLIES; HEAT FLUX; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS