Three-dimensional flow model development for thermal mixing and stratification modeling in reactor system transients analyses

Hu, Rui

doi:10.1016/j.nucengdes.2019.02.018

Title: Three-dimensional flow model development for thermal mixing and stratification modeling in reactor system transients analyses

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Abstract

Mixing, thermal-stratification, and mass transport phenomena in large pools or enclosures play major roles for the safety of reactor systems. Depending on the fidelity requirement and computational resources, various modeling methods, from the 0-D perfect mixing model to 3-D Computational Fluid Dynamics (CFD) models, are available. Each is associated with its own advantages and shortcomings. It is very desirable to develop an advanced and efficient thermal mixing and stratification modeling capability embedded in a modern system analysis code to improve the accuracy of reactor safety analyses and to reduce modeling uncertainties. An advanced system analysis tool, SAM, is being developed at Argonne National Laboratory for advanced non-LWR reactor safety analysis. While SAM is being developed as a system-level modeling and simulation tool, a reduced-order three-dimensional module is under development to model the mull-dimensional flow and thermal mixing and stratification in large enclosures of reactor systems. This paper provides an overview of the three-dimensional finite element flow model in SAM, including the governing equations, stabilization scheme, and solution methods. Additionally, several verification and validation tests are presented, including lid-driven cavity flow, natural convection inside a cavity, laminar flow in a channel of parallel plates. Here, based on the comparisons with themore »« less

Authors:

Hu, Rui ^[1]

Argonne National Lab. (ANL), Argonne, IL (United States)

Publication Date:: Tue Feb 26 00:00:00 EST 2019

Research Org.:: Argonne National Lab. (ANL), Argonne, IL (United States)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE), Nuclear Energy Advanced Modeling and Simulation (NEAMS); USDOE

OSTI Identifier:: 1510265

Alternate Identifier(s):: OSTI ID: 1636097

Grant/Contract Number:: AC02-06CH11357

Resource Type:: Accepted Manuscript

Journal Name:: Nuclear Engineering and Design

Additional Journal Information:: Journal Volume: 345; Journal Issue: C; Journal ID: ISSN 0029-5493

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 22 GENERAL STUDIES OF NUCLEAR REACTORS; CGCFD; pool modeling; reduced-order; thermal stratification

Citation Formats


                    Hu, Rui. Three-dimensional flow model development for thermal mixing and stratification modeling in reactor system transients analyses.  United States: N. p., 2019. 
Web.  doi:10.1016/j.nucengdes.2019.02.018.

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                    Hu, Rui. Three-dimensional flow model development for thermal mixing and stratification modeling in reactor system transients analyses.  United States.  https://doi.org/10.1016/j.nucengdes.2019.02.018

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                    Hu, Rui. Tue .  
"Three-dimensional flow model development for thermal mixing and stratification modeling in reactor system transients analyses".  United States.  https://doi.org/10.1016/j.nucengdes.2019.02.018.  https://www.osti.gov/servlets/purl/1510265.

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@article{osti_1510265,

  title        = {Three-dimensional flow model development for thermal mixing and stratification modeling in reactor system transients analyses},

  author       = {Hu, Rui},

  abstractNote = {Mixing, thermal-stratification, and mass transport phenomena in large pools or enclosures play major roles for the safety of reactor systems. Depending on the fidelity requirement and computational resources, various modeling methods, from the 0-D perfect mixing model to 3-D Computational Fluid Dynamics (CFD) models, are available. Each is associated with its own advantages and shortcomings. It is very desirable to develop an advanced and efficient thermal mixing and stratification modeling capability embedded in a modern system analysis code to improve the accuracy of reactor safety analyses and to reduce modeling uncertainties. An advanced system analysis tool, SAM, is being developed at Argonne National Laboratory for advanced non-LWR reactor safety analysis. While SAM is being developed as a system-level modeling and simulation tool, a reduced-order three-dimensional module is under development to model the mull-dimensional flow and thermal mixing and stratification in large enclosures of reactor systems. This paper provides an overview of the three-dimensional finite element flow model in SAM, including the governing equations, stabilization scheme, and solution methods. Additionally, several verification and validation tests are presented, including lid-driven cavity flow, natural convection inside a cavity, laminar flow in a channel of parallel plates. Here, based on the comparisons with the analytical solutions and experimental results, it is demonstrated that the developed 3-D fluid model can perform very well for a wide range of flow problems.},

  doi          = {10.1016/j.nucengdes.2019.02.018},

  journal      = {Nuclear Engineering and Design},

  number       = C,

  volume       = 345,

  place        = {United States},

  year         = {Tue Feb 26 00:00:00 EST 2019},

  month        = {Tue Feb 26 00:00:00 EST 2019}

}

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