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A novel friction factor model for wire-wrapped rod bundles.

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Title: A novel friction factor model for wire-wrapped rod bundles.
Authors: Dix, Adam1 (AUTHOR), Kim, Seungjin1 (AUTHOR) seungjin@purdue.edu
Source: Nuclear Engineering & Design. Jan2023, Vol. 401, pN.PAG-N.PAG. 1p.
Subjects: Friction, Fast reactors, Navier-Stokes equations, Nuclear reactors, Liquid metals
Abstract: • A novel friction factor model for wire-wrapped rod bundles is developed. • Exact solutions of the Navier-Stokes equations for a simplified bundle are used. • Model can predict experimental data with an average difference of 10.8%. • Theoretical minimum friction factor for a given geometry can be determined. Wire-wrapped rod bundles are often considered for fast spectrum nuclear reactors, especially liquid metal cooled fast reactors (LMFRs). Accurate calculation of the pressure drops of these bundles is key for proper thermal–hydraulic design of the reactor. Existing models, while able to accurately predict bundle friction factor, are complex and can be difficult to use without utilizing a numerical implementation. In this paper, a new model for bundle friction factor is proposed based on exact laminar solutions of the Navier-Stokes equations for a simplified rod bundle geometry. These exact solutions can then be adjusted via geometric and empirical parameters to the prototypic geometry. The proposed model is able to calculate the bundle friction factor with an average absolute percent difference of 10.8 % compared to the available experimental data. This compares favourably to existing correlations, offering similar performance while minimizing the number of empirical coefficients and the overall effort required. The model is also valuable for determining a theoretical lower bound for bundle friction factor for a given geometry, with some data found to be lower (>10 %) than this bound. The overall methodology can also in principal be applied to other geometries where similar simplifications could be made. [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: 160909615
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PubTypeId: academicJournal
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  Data: <searchLink fieldCode="DE" term="%22Friction%22">Friction</searchLink><br /><searchLink fieldCode="DE" term="%22Fast+reactors%22">Fast reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Navier-Stokes+equations%22">Navier-Stokes equations</searchLink><br /><searchLink fieldCode="DE" term="%22Nuclear+reactors%22">Nuclear reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Liquid+metals%22">Liquid metals</searchLink>
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  Data: • A novel friction factor model for wire-wrapped rod bundles is developed. • Exact solutions of the Navier-Stokes equations for a simplified bundle are used. • Model can predict experimental data with an average difference of 10.8%. • Theoretical minimum friction factor for a given geometry can be determined. Wire-wrapped rod bundles are often considered for fast spectrum nuclear reactors, especially liquid metal cooled fast reactors (LMFRs). Accurate calculation of the pressure drops of these bundles is key for proper thermal–hydraulic design of the reactor. Existing models, while able to accurately predict bundle friction factor, are complex and can be difficult to use without utilizing a numerical implementation. In this paper, a new model for bundle friction factor is proposed based on exact laminar solutions of the Navier-Stokes equations for a simplified rod bundle geometry. These exact solutions can then be adjusted via geometric and empirical parameters to the prototypic geometry. The proposed model is able to calculate the bundle friction factor with an average absolute percent difference of 10.8 % compared to the available experimental data. This compares favourably to existing correlations, offering similar performance while minimizing the number of empirical coefficients and the overall effort required. The model is also valuable for determining a theoretical lower bound for bundle friction factor for a given geometry, with some data found to be lower (>10 %) than this bound. The overall methodology can also in principal be applied to other geometries where similar simplifications could be made. [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:
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      – Type: doi
        Value: 10.1016/j.nucengdes.2022.112104
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      – Code: eng
        Text: English
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        PageCount: 1
        StartPage: N.PAG
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      – SubjectFull: Friction
        Type: general
      – SubjectFull: Fast reactors
        Type: general
      – SubjectFull: Navier-Stokes equations
        Type: general
      – SubjectFull: Nuclear reactors
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      – SubjectFull: Liquid metals
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              M: 01
              Text: Jan2023
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              Y: 2023
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              Value: 401
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