Published 2005
| Version v1
Miscellaneous
Critical heat flux, single-phase and two-phase pressure drop methodologies for CANFLEX-NU with crept and uncrept pressure tubes
Creators
- 1. Nuclear Safety Solutions (NSS) Ltd., Toronto, Ontario (Canada)
Description
Methodologies were developed for pressure drop (single and two-phase), Onset of Significant Void and local conditions Critical Heat Flux applicable to crept and uncrept fuel channels containing 43-element CANFLEX Natural Uranium (NU) fuel bundles. The correlations are based on the Stern Laboratory Incorporated experimental data for CANFLEX NU design. To obtain the coefficients for the different correlations developed, the Gauss-Newton method for unconstrained optimization problems was employed. Excellent agreement was obtained between experimental data and the predictions of the developed correlations. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 0-919784-84-4
- Imprint Title
- Ninth international conference on CANDU fuel, 'fuelling a clean future'
- Imprint Pagination
- 152 Megabytes
- Journal Page Range
- [11 p.]
Conference
- Title
- 9. International conference on CANDU fuel, 'fuelling a clean future'. Proceedings
- Dates
- 18-21 Sep 2005
- Place
- Belleville, Ontario (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 38109990
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data, Non-conventional Literature
- Descriptors DEI
- CREEP; CRITICAL HEAT FLUX; EXPERIMENTAL DATA; FUEL CHANNELS; FUEL ELEMENT CLUSTERS; NATURAL URANIUM
- Descriptors DEC
- ACTINIDES; DATA; ELEMENTS; FUEL ASSEMBLIES; HEAT FLUX; INFORMATION; MECHANICAL PROPERTIES; METALS; NUMERICAL DATA; REACTOR CHANNELS; REACTOR COMPONENTS; URANIUM
Optional Information
- Notes
- Paper B1001; 1 ref., 3 figs.