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

  • 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)

Part of:
ISSCWR-9. The 9th International Symposium on Supercritical-Water-Cooled Reactors

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.