Verification and validation of COMSOL for heat transfer in thin rectangular channels using NACA test results [1]

T. K. Howard, P. Jain, E. Popov

Research output: Contribution to conferencePaperpeer-review

1 Scopus citations

Abstract

Currently efforts are underway at Oak Ridge National Laboratory to convert the High Flux Isotope Reactor (HFIR) from high-enriched uranium to low-enriched uranium fuel. To provide confidence to the thermal hydraulics calculations, computational fluid dynamics (CFD) simulations—simulated using COMOSOL—have been used to calculate the pressure drop and heat transfer in the coolant. While CFD simulations provide well-resolved results, turbulence models include many assumptions and must be validated for use in any safety-based analysis. In HFIR, long, thin involute fuel plates are separated by coolant channels of equal size. The coolant channels are best described as thin rectangular channels. Unfortunately, there are few studies verifying and validating CFD for use in thin rectangular channels. This study seeks to bridge that gap by verifying, validating, and comparing various CFD models used in thin channels. To verify and validate CFD for use in thin channels, a series of simple analytic test cases are used, and the method of manufactured solutions (MMS) is used to further verify the COMSOL tool and mesh geometry. For the validation, a series of tests conducted at the National Aeronautics and Space Administration were simulated in COMSOL. The results of this study are threefold. First, it verifies the ability of COMSOL to model heat transfer in thin channels. Second, it addresses the various aspects of CFD modeling that are of greatest concern for heat transfer simulations in the geometry. Third, and finally, it discusses the ability of various CFD models used in COMSOL to accurately predict heat transfer in narrow rectangular channels.

Original languageEnglish
Pages3598-3611
Number of pages14
StatePublished - 2019
Event18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 - Portland, United States
Duration: Aug 18 2019Aug 23 2019

Conference

Conference18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019
Country/TerritoryUnited States
CityPortland
Period08/18/1908/23/19

Funding

* Notice: This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doepublic-access-plan). Notice: This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doepublic-access-plan).

FundersFunder number
DOE Public Access Plan
US Department of Energy
UT-BattelleDE-AC05-00OR22725
U.S. Department of Energy

    Keywords

    • COMSOL
    • Fuel Plates
    • Thin Channels
    • Verification and Validation

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