Newton-Krylov method in solving drift-flux two-phase flow problems for both pre-CHF and post-CHF conditions at steady state

Zou, Ling; Zhao, Haihua; Zhang, Hongbin

doi:10.1016/j.anucene.2017.10.038

Title: Newton-Krylov method in solving drift-flux two-phase flow problems for both pre-CHF and post-CHF conditions at steady state

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Abstract

Furthermore, this paper presents numerical simulations of two-phase flow heat transfer for both pre-CHF and post-CHF conditions typical in light water nuclear reactors. The conjugate heat transfer problem is modeled with one-dimensional drift-flux two-phase flow model for coolant flow and two-dimensional heat conduction equation in solid walls. Fully implicit time integration schemes were employed, and the resulted non-linear equations were solved with a Newton-Krylov method. For the drift-flux two-phase flow model, the EPRI drift-flux closure correlation is used to model the relative motion between the two phases. Additional closure correlations were adopted from REALP5-3D to determine two-phase flow regime, wall boiling heat and mass transfer, interfacial heat and mass transfer, and two-phase flow frictional pressure drop. Three sets of experiments were used for code validation, including Bartolomei subcooled flow boiling in vertical pipes, FRIGG boiling tests in vertical bundles, and Bennett heated tube tests. RELAP5-3D simulation results were also provided to perform code-to-code benchmark. Overall, numerical results of this work showed good agreements with both experimental data and RELAP5-3D simulation results. Discrepancy between them were also identified in post-CHF region, which suggests necessary further improvement.

Authors:

^[1]; Zhao, Haihua ^[1];

^[1]

Idaho National Lab. (INL), Idaho Falls, ID (United States)

Publication Date:: Sun Nov 05 00:00:00 EDT 2017

Research Org.:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE)

OSTI Identifier:: 1480427

Alternate Identifier(s):: OSTI ID: 1549511

Report Number(s):: INL/JOU-17-42573-Rev000
Journal ID: ISSN 0306-4549

Grant/Contract Number:: AC07-05ID14517

Resource Type:: Accepted Manuscript

Journal Name:: Annals of Nuclear Energy (Oxford)

Additional Journal Information:: Journal Name: Annals of Nuclear Energy (Oxford); Journal Volume: 112; Journal Issue: C; Journal ID: ISSN 0306-4549

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 42 ENGINEERING; 97 MATHEMATICS AND COMPUTING; Newton-Krylov method; Drift-flux model; Pre-CHF and post-CHF heat transfer

Citation Formats


                    Zou, Ling, Zhao, Haihua, and Zhang, Hongbin. Newton-Krylov method in solving drift-flux two-phase flow problems for both pre-CHF and post-CHF conditions at steady state.  United States: N. p., 2017. 
Web.  doi:10.1016/j.anucene.2017.10.038.

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                    Zou, Ling, Zhao, Haihua, & Zhang, Hongbin. Newton-Krylov method in solving drift-flux two-phase flow problems for both pre-CHF and post-CHF conditions at steady state.  United States.  https://doi.org/10.1016/j.anucene.2017.10.038

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                    Zou, Ling, Zhao, Haihua, and Zhang, Hongbin. Sun .  
"Newton-Krylov method in solving drift-flux two-phase flow problems for both pre-CHF and post-CHF conditions at steady state".  United States.  https://doi.org/10.1016/j.anucene.2017.10.038.  https://www.osti.gov/servlets/purl/1480427.

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@article{osti_1480427,

  title        = {Newton-Krylov method in solving drift-flux two-phase flow problems for both pre-CHF and post-CHF conditions at steady state},

  author       = {Zou, Ling and Zhao, Haihua and Zhang, Hongbin},

  abstractNote = {Furthermore, this paper presents numerical simulations of two-phase flow heat transfer for both pre-CHF and post-CHF conditions typical in light water nuclear reactors. The conjugate heat transfer problem is modeled with one-dimensional drift-flux two-phase flow model for coolant flow and two-dimensional heat conduction equation in solid walls. Fully implicit time integration schemes were employed, and the resulted non-linear equations were solved with a Newton-Krylov method. For the drift-flux two-phase flow model, the EPRI drift-flux closure correlation is used to model the relative motion between the two phases. Additional closure correlations were adopted from REALP5-3D to determine two-phase flow regime, wall boiling heat and mass transfer, interfacial heat and mass transfer, and two-phase flow frictional pressure drop. Three sets of experiments were used for code validation, including Bartolomei subcooled flow boiling in vertical pipes, FRIGG boiling tests in vertical bundles, and Bennett heated tube tests. RELAP5-3D simulation results were also provided to perform code-to-code benchmark. Overall, numerical results of this work showed good agreements with both experimental data and RELAP5-3D simulation results. Discrepancy between them were also identified in post-CHF region, which suggests necessary further improvement.},

  doi          = {10.1016/j.anucene.2017.10.038},

  journal      = {Annals of Nuclear Energy (Oxford)},

  number       = C,

  volume       = 112,

  place        = {United States},

  year         = {Sun Nov 05 00:00:00 EDT 2017},

  month        = {Sun Nov 05 00:00:00 EDT 2017}

}

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