Nek5000 Large-Eddy Simulations for Thermal-Hydraulics of Deformed Wire-Wrap Fuel Assemblies
- 1. Argonne National Laboratory, Argonne, IL (United States)
- 2. University of Illinois at Urbana-Champaign, Urbana, IL (United States)
Description
A well-characterized validation program has been defined for the thermal-hydraulic CFD modeling of 61-pin hexagonal packed fuel assemblies with helically wire-wrapped pins for both non-deformed beginning-of-life geometries and deformed later-in-life geometries typical of sodium-cooled fast reactors. The motivation for this work is the need to validate CFD codes to accurately model the flow and thermal performance of wire-wrapped fuel assemblies, particularly the deformed later-in-life bundles. The effect of pin and duct deformation is increasingly important as reactor designs look toward longer assembly lifetimes. As a part of a larger collaborative project with TerraPower, Texas A and M University (TAMU), and AREVA, this validation work consists of CFD simulations of four con-current experiments. Pre-test numerical simulations corresponding to each of the experiments has been conducted and are planned to be followed by post-test simulations that will incorporate test information as it becomes available to account for any as-built differences in geometry of test section and its specifications including the differences in boundary conditions of the actual tests. This paper focuses on Nek5000 LES results for the isothermal/TAMU undeformed configuration as a first step toward and initial conditions for the deformed isothermal/TAMU and/or conjugate heat transfer/AREVA cases. (authors)
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 115
- Journal Page Range
- p. 1491-1494
- ISSN
- 0003-018X
Conference
- Title
- 2016 ANS Winter Meeting and Nuclear Technology Expo
- Dates
- 6-10 Nov 2016
- Place
- Las Vegas, NV (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52083256
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOUNDARY CONDITIONS; FUEL ASSEMBLIES; GEOMETRY; HEAT TRANSFER; LARGE-EDDY SIMULATION; PERFORMANCE; REACTOR DESIGN; SODIUM COOLED REACTORS; SPECIFICATIONS; THERMAL HYDRAULICS; VALIDATION; WIRES
- Descriptors DEC
- COMPUTERIZED SIMULATION; DESIGN; ENERGY TRANSFER; FLUID MECHANICS; HYDRAULICS; LIQUID METAL COOLED REACTORS; MATHEMATICS; MECHANICS; REACTOR LIFE CYCLE; REACTORS; SIMULATION; TESTING
Optional Information
- Notes
- 4 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)