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An application of the nodal expansion method to the determination of the radial temperature distribution in a nuclear fuel rod.

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Title: An application of the nodal expansion method to the determination of the radial temperature distribution in a nuclear fuel rod.
Authors: Dall’Osso, Aldo1 aldo.dallosso@areva.com, Brault, Léandre1
Source: Annals of Nuclear Energy. May2018, Vol. 115, p9-15. 7p.
Subjects: FORTRAN, Nuclear reactors, Algebra software, Macsyma (Computer software), Nuclear fuels
Abstract: Within nuclear reactor simulation codes, the temperature distribution inside the fuel rod is computed with a mono-dimensional cylindrical heat conduction model. The main discretization methods applied to reduce the differential equation into an algebraic system are the finite difference or the finite volume method. These methods require a fine mesh to obtain accurate fuel temperature distributions. We explore here the applicability of the Nodal Expansion Method (NEM) limited to the second order. The results on some steady state examples show a good performance of the method. The development of the solver has been carried out with the Computer Algebra System Mathematica associated to the package MathCompile , which enables to follow the various development steps from the specification of the method to the FORTRAN programming and numerical verification. [ABSTRACT FROM AUTHOR]
Copyright of Annals of Nuclear Energy is the property of Pergamon Press - An Imprint of Elsevier Science 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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Header DbId: egs
DbLabel: Engineering Source
An: 128277468
AccessLevel: 6
PubType: Academic Journal
PubTypeId: academicJournal
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  Data: An application of the nodal expansion method to the determination of the radial temperature distribution in a nuclear fuel rod.
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  Data: <searchLink fieldCode="JN" term="%22Annals+of+Nuclear+Energy%22">Annals of Nuclear Energy</searchLink>. May2018, Vol. 115, p9-15. 7p.
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  Label: Abstract
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  Data: Within nuclear reactor simulation codes, the temperature distribution inside the fuel rod is computed with a mono-dimensional cylindrical heat conduction model. The main discretization methods applied to reduce the differential equation into an algebraic system are the finite difference or the finite volume method. These methods require a fine mesh to obtain accurate fuel temperature distributions. We explore here the applicability of the Nodal Expansion Method (NEM) limited to the second order. The results on some steady state examples show a good performance of the method. The development of the solver has been carried out with the Computer Algebra System Mathematica associated to the package MathCompile , which enables to follow the various development steps from the specification of the method to the FORTRAN programming and numerical verification. [ABSTRACT FROM AUTHOR]
– Name: AbstractSuppliedCopyright
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  Group: Ab
  Data: <i>Copyright of Annals of Nuclear Energy is the property of Pergamon Press - An Imprint of Elsevier Science 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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      – Type: doi
        Value: 10.1016/j.anucene.2018.01.006
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      – Code: eng
        Text: English
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        PageCount: 7
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      – SubjectFull: FORTRAN
        Type: general
      – SubjectFull: Nuclear reactors
        Type: general
      – SubjectFull: Algebra software
        Type: general
      – SubjectFull: Macsyma (Computer software)
        Type: general
      – SubjectFull: Nuclear fuels
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      – TitleFull: An application of the nodal expansion method to the determination of the radial temperature distribution in a nuclear fuel rod.
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              Text: May2018
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              Y: 2018
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