Published 2019
| Version v1
Miscellaneous
A numerical study of turbulent upward flow of super critical water in a 2X2 rod bundle with non-uniform heating
Creators
- 1. University of Sheffield, Dept. of Mechanical Engineering, Sheffield (United Kingdom)
- 2. Daresbury Laboratory, Science and Technology Facilities Council, Warrington (United Kingdom)
- 3. EDF Energy R&D UK Centre, Manchester (United Kingdom)
Description
This work is part of a benchmarking excise organized by IAEA CRP in SCWR thermalhydraulics aimed at improving the understanding and prediction accuracy of the thermalhydraulic phenomena relevant to SCWRs. An experiment carried out using a 2×2 SCWR bundle at University of Wisconsin-Madison was modelled using an open-source CFD code (Code_Saturne). The k-ω SST model was employed to account for the buoyancy-aided turbulent flow in the fuel channel. Significant heat transfer deterioration was observed in the boundary layer, which is commonly expected to occur in buoyancy-aided flows. For comparison, simulations were also conducted using ANSYS FLUENT with similar model setups. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- Imprint Title
- ISSCWR-9. The 9th International Symposium on Supercritical-Water-Cooled Reactors
- Imprint Pagination
- [62 Mb]
- Journal Page Range
- [13 p.]
Conference
- Title
- 9. International Symposium on Supercritical-Water-Cooled Reactors
- Dates
- 10-14 Mar 2019
- Place
- Vancouver, British Columbia (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 52015738
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; FLUID MECHANICS; FUEL ELEMENT CLUSTERS; FUEL RODS; HEAT TRANSFER; SUPERCRITICAL STATE; TURBULENT FLOW; WATER COOLED REACTORS
- Descriptors DEC
- ENERGY TRANSFER; FLUID FLOW; FUEL ASSEMBLIES; FUEL ELEMENTS; MECHANICS; REACTOR COMPONENTS; REACTORS; SIMULATION
Optional Information
- Notes
- 33 refs., 1 tab., 7 figs.