Thermalhydraulics and safety research in support of Phase-II of the Canadian Generation-IV national program
Description
The thermalhydraulics and safety projects in the Phase-II of the Canadian National Program for Gen-IV Energy Technologies have been established to (i) provide relevant experimental data for verification and validation of prediction methods and analytical toolsets developed in Phase-I, and (ii) improve the accuracy of prediction methods in support of fuel assembly optimization and safety analyses. Several experimental projects are currently being carried out to obtain heat-transfer data with annuli, 3-rod assembly, and 4-rod assembly in refrigerant- 134a flow, carbon dioxide flow, and water flow, and blow-down and natural-circulation data with tubes in water and carbon dioxide flow, respectively. These experimental data have led to improved understanding of the thermalhydraulics phenomena and enhanced the prediction accuracy of parameters. Prediction methods for thermalhydraulics parameters have been derived to support the fuel optimization and safety analyses. This has led to improved confidence in the development of the Canadian SCWR concept. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 978-1-926773-16-2
- Imprint Title
- PBNC 2014 : 19th Pacific Basin Nuclear Conference; 38th Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association
- Imprint Pagination
- 270 Megabytes
- Journal Page Range
- [16 p.]
Conference
- Title
- 19. Pacific Basin Nuclear Conference; 38. Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association
- Dates
- 24-28 Aug 2014
- Place
- Vancouver, British Columbia (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 49016158
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature, Numerical Data
- Descriptors DEI
- EXPERIMENTAL DATA; HEAT TRANSFER; NATURAL CONVECTION; REACTOR SAFETY; SUPERCRITICAL STATE; THERMAL HYDRAULICS; TURBULENT FLOW; WATER COOLED REACTORS
- Descriptors DEC
- CONVECTION; DATA; ENERGY TRANSFER; FLUID FLOW; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; INFORMATION; MASS TRANSFER; MECHANICS; NUMERICAL DATA; REACTORS; SAFETY
Optional Information
- Notes
- Paper PBNC2014-056. 20 refs., 1 tab., 12 figs.