Quantifying HFIR Turbulence by Variable Curvature Channels

Nicholas J. Mecham, Igor A. Bolotnov, Emilian L. Popov

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

1 Scopus citations

Abstract

The Oak Ridge National Laboratory (ORNL) High Flux Isotope Reactor (HFIR) is a very high-flux, pressurized, light water-cooled, flux trap -type research reactor whose current missions are to support neutron scattering experiments, isotope production, materials irradiation, and neutron activation analysis. Because it is difficult to instrument experiments in HFIR's narrow channels, high-fidelity numerical data are needed to verify and calibrate the Reynolds-averaged Navier-Stokes models that are routinely used. Direct numerical simulation (DNS) of the entire spanwise HFIR channel necessitates large, computationally expensive meshes to resolve the turbulence scales because of relatively high velocity flow. It is therefore desirable to determine whether statistically similar turbulence results can be obtained via DNS of smaller domains with comparable curvatures. DNS of coolant flow in several channels of varying curvature was performed at a hydraulic diameter-based Reynolds number of about 70,000. Various locations along the span of the involute HFIR channel were analyzed to assess the effect of curvature on the turbulent flow parameters. Turbulence statistics were collected and compared with HFIR channel results to assess whether a channel with constant curvature and a smaller arc length yields similar results for a location of matching curvature on the HFIR involute geometry. The statistical steadiness of the flow was assessed using conventional total stress relations for flat channels; the applicability of these relations to curved channels is discussed. Mean velocity profiles, turbulent kinetic energy, and turbulence dissipation rates are compared. Higher order turbulence transport terms were calculated and are discussed briefly.

Original languageEnglish
Title of host publicationProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PublisherAmerican Nuclear Society
Pages1194-1205
Number of pages12
ISBN (Electronic)9780894487934
DOIs
StatePublished - 2023
Event20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 - Washington, United States
Duration: Aug 20 2023Aug 25 2023

Publication series

NameProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023

Conference

Conference20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
Country/TerritoryUnited States
CityWashington
Period08/20/2308/25/23

Funding

This work was supported by the National Nuclear Security Administration Office of Material Management and Minimization, US Department of Energy. The solution presented here uses the Acusim linear algebra solution library provided by Altair Engineering Inc, and meshing and geometric modeling libraries are provided by Simmetrix Inc. The high-performance computing resources were provided by National Energy Research Scientific Computing and Argonne Leadership Computing Facility allocations.

FundersFunder number
Simmetrix Inc.
National Nuclear Security Administration Office of Material Management and Minimization
U.S. Department of Energy
National Energy Research Scientific Computing and Argonne Leadership Computing Facility allocations
Altair Engineering Inc

    Keywords

    • Direct Numerical Simulation
    • HFIR
    • Turbulent Flow

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