A computationally efficient method for full-core conjugate heat transfer modeling of sodium fast reactors

Hu, Rui; Yu, Yiqi

doi:10.1016/j.nucengdes.2016.08.018

Title: A computationally efficient method for full-core conjugate heat transfer modeling of sodium fast reactors

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Abstract

For efficient and accurate temperature predictions of sodium fast reactor structures, a 3-D full-core conjugate heat transfer modeling capability is developed for an advanced system analysis tool, SAM. The hexagon lattice core is modeled with 1-D parallel channels representing the subassembly flow, and 2-D duct walls and inter-assembly gaps. The six sides of the hexagon duct wall and near-wall coolant region are modeled separately to account for different temperatures and heat transfer between coolant flow and each side of the duct wall. The Jacobian Free Newton Krylov (JFNK) solution method is applied to solve the fluid and solid field simultaneously in a fully coupled fashion. The 3-D full-core conjugate heat transfer modeling capability in SAM has been demonstrated by a verification test problem with 7 fuel assemblies in a hexagon lattice layout. In addition, the SAM simulation results are compared with RANS-based CFD simulations. Very good agreements have been achieved between the results of the two approaches.

Authors:

Hu, Rui ^[1]; Yu, Yiqi ^[1]

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

Publication Date:: Thu Sep 08 00:00:00 EDT 2016

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)

OSTI Identifier:: 1339576

Alternate Identifier(s):: OSTI ID: 1397894

Grant/Contract Number:: AC02-06CH11357

Resource Type:: Accepted Manuscript

Journal Name:: Nuclear Engineering and Design

Additional Journal Information:: Journal Volume: 308; Journal Issue: C; Journal ID: ISSN 0029-5493

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; JFNK; conjugate heat transfer; sodium fast reactor; system thermal-hydraulics

Citation Formats


                    Hu, Rui, and Yu, Yiqi. A computationally efficient method for full-core conjugate heat transfer modeling of sodium fast reactors.  United States: N. p., 2016. 
Web.  doi:10.1016/j.nucengdes.2016.08.018.

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                    Hu, Rui, & Yu, Yiqi. A computationally efficient method for full-core conjugate heat transfer modeling of sodium fast reactors.  United States.  https://doi.org/10.1016/j.nucengdes.2016.08.018

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                    Hu, Rui, and Yu, Yiqi. Thu .  
"A computationally efficient method for full-core conjugate heat transfer modeling of sodium fast reactors".  United States.  https://doi.org/10.1016/j.nucengdes.2016.08.018.  https://www.osti.gov/servlets/purl/1339576.

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@article{osti_1339576,

  title        = {A computationally efficient method for full-core conjugate heat transfer modeling of sodium fast reactors},

  author       = {Hu, Rui and Yu, Yiqi},

  abstractNote = {For efficient and accurate temperature predictions of sodium fast reactor structures, a 3-D full-core conjugate heat transfer modeling capability is developed for an advanced system analysis tool, SAM. The hexagon lattice core is modeled with 1-D parallel channels representing the subassembly flow, and 2-D duct walls and inter-assembly gaps. The six sides of the hexagon duct wall and near-wall coolant region are modeled separately to account for different temperatures and heat transfer between coolant flow and each side of the duct wall. The Jacobian Free Newton Krylov (JFNK) solution method is applied to solve the fluid and solid field simultaneously in a fully coupled fashion. The 3-D full-core conjugate heat transfer modeling capability in SAM has been demonstrated by a verification test problem with 7 fuel assemblies in a hexagon lattice layout. In addition, the SAM simulation results are compared with RANS-based CFD simulations. Very good agreements have been achieved between the results of the two approaches.},

  doi          = {10.1016/j.nucengdes.2016.08.018},

  journal      = {Nuclear Engineering and Design},

  number       = C,

  volume       = 308,

  place        = {United States},

  year         = {Thu Sep 08 00:00:00 EDT 2016},

  month        = {Thu Sep 08 00:00:00 EDT 2016}

}

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