Validation of NEPTUNE CFD two-phase flow models against OECD/NRC PSBT subchannel experiments.
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| Title: | Validation of NEPTUNE CFD two-phase flow models against OECD/NRC PSBT subchannel experiments. |
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| Authors: | Lutsanych, S.1 s.lutsanych@ing.unipi.it, Moretti, F.1,2 f.moretti@nineeng.com, D'Auria, F.1 f.dauria@ing.unipi.it |
| Source: | Nuclear Engineering & Design. Sep2017, Vol. 321, p82-91. 10p. |
| Subjects: | Computational fluid dynamics, Two-phase flow, Nuclear physics experiments, Sensitivity analysis, Axial loads |
| Abstract: | This paper deals with the validation of the multifield computational fluid dynamics code NEPTUNE_CFD v2.0.1 against experimental data available from the OECD/NRC NUPEC PWR subchannel and bundle tests (PSBT) international benchmark. The present work is performed in the framework of the NURESAFE European collaborative project and focuses on the steady-state single subchannel void fraction tests. From overall 126 PSBT experiments covering wide range of test conditions and 4 different geometrical configurations of PWR subchannel, 42 tests have been selected and simulated using NEPTUNE_CFD. Following the NEA/CSNI (Nuclear Energy Agency/Committee on the Safety of Nuclear Installations) best practice guidelines about computational grid design and grid quality, mesh sensitivity analysis has been performed using axial and radial grid refinement. Both axial and radial mesh sensitivity studies do not exhibit any significant change in the predicted results, which thus result to be grid-converged. Besides, a series of sensitivity calculations have been performed in order to investigate the influence of uncertainties of the experimental boundary conditions on the code predictions. The influence of code physical and closure models on the void fraction prediction has been studied and discussed in detail. Generally, the calculated cross-sectional averaged void fraction at the measurement plane differs from the measured one by maximum of ±8%. This discrepancy is comparable to the 2σ experimental uncertainty range on void fraction measurement. The performed investigations have shown the ability of NEPTUNE_CFD to predict reasonably the void fraction in PSBT subchannel using appropriate modeling. [ABSTRACT FROM AUTHOR] |
| Copyright of Nuclear Engineering & Design is the property of Elsevier B.V. and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.) | |
| Database: | Engineering Source |
| FullText | Text: Availability: 0 |
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| Header | DbId: egs DbLabel: Engineering Source An: 125286534 AccessLevel: 6 PubType: Academic Journal PubTypeId: academicJournal PreciseRelevancyScore: 0 |
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| Items | – Name: Title Label: Title Group: Ti Data: Validation of NEPTUNE CFD two-phase flow models against OECD/NRC PSBT subchannel experiments. – Name: Author Label: Authors Group: Au Data: <searchLink fieldCode="AR" term="%22Lutsanych%2C+S%2E%22">Lutsanych, S.</searchLink><relatesTo>1</relatesTo><i> s.lutsanych@ing.unipi.it</i><br /><searchLink fieldCode="AR" term="%22Moretti%2C+F%2E%22">Moretti, F.</searchLink><relatesTo>1,2</relatesTo><i> f.moretti@nineeng.com</i><br /><searchLink fieldCode="AR" term="%22D'Auria%2C+F%2E%22">D'Auria, F.</searchLink><relatesTo>1</relatesTo><i> f.dauria@ing.unipi.it</i> – Name: TitleSource Label: Source Group: Src Data: <searchLink fieldCode="JN" term="%22Nuclear+Engineering+%26+Design%22">Nuclear Engineering & Design</searchLink>. Sep2017, Vol. 321, p82-91. 10p. – Name: Subject Label: Subjects Group: Su Data: <searchLink fieldCode="DE" term="%22Computational+fluid+dynamics%22">Computational fluid dynamics</searchLink><br /><searchLink fieldCode="DE" term="%22Two-phase+flow%22">Two-phase flow</searchLink><br /><searchLink fieldCode="DE" term="%22Nuclear+physics+experiments%22">Nuclear physics experiments</searchLink><br /><searchLink fieldCode="DE" term="%22Sensitivity+analysis%22">Sensitivity analysis</searchLink><br /><searchLink fieldCode="DE" term="%22Axial+loads%22">Axial loads</searchLink> – Name: Abstract Label: Abstract Group: Ab Data: This paper deals with the validation of the multifield computational fluid dynamics code NEPTUNE_CFD v2.0.1 against experimental data available from the OECD/NRC NUPEC PWR subchannel and bundle tests (PSBT) international benchmark. The present work is performed in the framework of the NURESAFE European collaborative project and focuses on the steady-state single subchannel void fraction tests. From overall 126 PSBT experiments covering wide range of test conditions and 4 different geometrical configurations of PWR subchannel, 42 tests have been selected and simulated using NEPTUNE_CFD. Following the NEA/CSNI (Nuclear Energy Agency/Committee on the Safety of Nuclear Installations) best practice guidelines about computational grid design and grid quality, mesh sensitivity analysis has been performed using axial and radial grid refinement. Both axial and radial mesh sensitivity studies do not exhibit any significant change in the predicted results, which thus result to be grid-converged. Besides, a series of sensitivity calculations have been performed in order to investigate the influence of uncertainties of the experimental boundary conditions on the code predictions. The influence of code physical and closure models on the void fraction prediction has been studied and discussed in detail. Generally, the calculated cross-sectional averaged void fraction at the measurement plane differs from the measured one by maximum of ±8%. This discrepancy is comparable to the 2σ experimental uncertainty range on void fraction measurement. The performed investigations have shown the ability of NEPTUNE_CFD to predict reasonably the void fraction in PSBT subchannel using appropriate modeling. [ABSTRACT FROM AUTHOR] – Name: AbstractSuppliedCopyright Label: Group: Ab Data: <i>Copyright of Nuclear Engineering & Design is the property of Elsevier B.V. and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.) |
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| RecordInfo | BibRecord: BibEntity: Identifiers: – Type: doi Value: 10.1016/j.nucengdes.2017.02.005 Languages: – Code: eng Text: English PhysicalDescription: Pagination: PageCount: 10 StartPage: 82 Subjects: – SubjectFull: Computational fluid dynamics Type: general – SubjectFull: Two-phase flow Type: general – SubjectFull: Nuclear physics experiments Type: general – SubjectFull: Sensitivity analysis Type: general – SubjectFull: Axial loads Type: general Titles: – TitleFull: Validation of NEPTUNE CFD two-phase flow models against OECD/NRC PSBT subchannel experiments. Type: main BibRelationships: HasContributorRelationships: – PersonEntity: Name: NameFull: Lutsanych, S. – PersonEntity: Name: NameFull: Moretti, F. – PersonEntity: Name: NameFull: D'Auria, F. IsPartOfRelationships: – BibEntity: Dates: – D: 01 M: 09 Text: Sep2017 Type: published Y: 2017 Identifiers: – Type: issn-print Value: 00295493 Numbering: – Type: volume Value: 321 Titles: – TitleFull: Nuclear Engineering & Design Type: main |
| ResultId | 1 |
