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Numerical simulation of flow and mixing in ROCOM facility using uniform and non-uniform inlet flow velocity profiles.

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Title: Numerical simulation of flow and mixing in ROCOM facility using uniform and non-uniform inlet flow velocity profiles.
Authors: Boumaza, M.1 m_boumaza03@hotmail.fr, Moretti, F.2, Dizene, R.3
Source: Nuclear Engineering & Design. Dec2014, Vol. 280, p362-371. 10p.
Subjects: Pressurized water reactors, Fluid flow, Computer simulation, Thermal shock, Computational fluid dynamics
Abstract: Water loss and depressurization of the primary circuit of a PWR lead to the actuation of the safety injection system (ECC). The cold water injected in the cold legs of the primary circuit is mixed partially with high temperature water. The cold water may cause a thermal shock to the reactor pressure vessel (RPV). The latter is more severe if the safety injection water enters the reactor vessel without mixing beforehand. The simulation and assessment of the mixing can be made using CFD codes. In the present framework, three-dimensional simulations are carried out using the CFD code ANSYS CFX, to investigate the mixing phenomenon in the Rossendorf Coolant Mixing Model (ROCOM) test facility. The predicted flow vertical velocity and tracer concentration distributions are presented and compared to the experimental data. Furthermore, the impact of the inlet velocity profile on the numerical results is assessed. The present results seem to confirm the capability of the CFD modeling to simulate the mixing phenomenon, which remains a key parameter for predicting the whole RPV behavior under abnormal cooling conditions. [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
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DbLabel: Engineering Source
An: 99792026
AccessLevel: 6
PubType: Academic Journal
PubTypeId: academicJournal
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  Data: Numerical simulation of flow and mixing in ROCOM facility using uniform and non-uniform inlet flow velocity profiles.
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  Data: <searchLink fieldCode="AR" term="%22Boumaza%2C+M%2E%22">Boumaza, M.</searchLink><relatesTo>1</relatesTo><i> m_boumaza03@hotmail.fr</i><br /><searchLink fieldCode="AR" term="%22Moretti%2C+F%2E%22">Moretti, F.</searchLink><relatesTo>2</relatesTo><br /><searchLink fieldCode="AR" term="%22Dizene%2C+R%2E%22">Dizene, R.</searchLink><relatesTo>3</relatesTo>
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  Data: <searchLink fieldCode="JN" term="%22Nuclear+Engineering+%26+Design%22">Nuclear Engineering & Design</searchLink>. Dec2014, Vol. 280, p362-371. 10p.
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  Data: <searchLink fieldCode="DE" term="%22Pressurized+water+reactors%22">Pressurized water reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Fluid+flow%22">Fluid flow</searchLink><br /><searchLink fieldCode="DE" term="%22Computer+simulation%22">Computer simulation</searchLink><br /><searchLink fieldCode="DE" term="%22Thermal+shock%22">Thermal shock</searchLink><br /><searchLink fieldCode="DE" term="%22Computational+fluid+dynamics%22">Computational fluid dynamics</searchLink>
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  Data: Water loss and depressurization of the primary circuit of a PWR lead to the actuation of the safety injection system (ECC). The cold water injected in the cold legs of the primary circuit is mixed partially with high temperature water. The cold water may cause a thermal shock to the reactor pressure vessel (RPV). The latter is more severe if the safety injection water enters the reactor vessel without mixing beforehand. The simulation and assessment of the mixing can be made using CFD codes. In the present framework, three-dimensional simulations are carried out using the CFD code ANSYS CFX, to investigate the mixing phenomenon in the Rossendorf Coolant Mixing Model (ROCOM) test facility. The predicted flow vertical velocity and tracer concentration distributions are presented and compared to the experimental data. Furthermore, the impact of the inlet velocity profile on the numerical results is assessed. The present results seem to confirm the capability of the CFD modeling to simulate the mixing phenomenon, which remains a key parameter for predicting the whole RPV behavior under abnormal cooling conditions. [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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        Value: 10.1016/j.nucengdes.2014.10.018
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      – Code: eng
        Text: English
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        PageCount: 10
        StartPage: 362
    Subjects:
      – SubjectFull: Pressurized water reactors
        Type: general
      – SubjectFull: Fluid flow
        Type: general
      – SubjectFull: Computer simulation
        Type: general
      – SubjectFull: Thermal shock
        Type: general
      – SubjectFull: Computational fluid dynamics
        Type: general
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      – TitleFull: Numerical simulation of flow and mixing in ROCOM facility using uniform and non-uniform inlet flow velocity profiles.
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            – D: 01
              M: 12
              Text: Dec2014
              Type: published
              Y: 2014
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              Value: 280
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