Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA)

M. Scheuerer (Corresponding Author), M. Heitsch, F. Menter, Y. Egorov, I. Toth, D. Bestion, S. Pigny, H. Paillere, A. Martin, M. Boucker, E. Krepper, S. Willemsen, P. Muhlbauer, M. Andreani, B. Smith, R. Karlsson, M. Henriksson, B. Hemstrom, Ismo Karppinen, G. Kimber

    Research output: Contribution to journalArticleScientificpeer-review

    47 Citations (Scopus)

    Abstract

    The objective of the ECORA project is the evaluation of computational fluid dynamics (CFD) software for reactor safety applications, resulting in best practice guidelines (BPG) for an efficient use of CFD for reactor safety problems. The project schedule is as follows: (i) establishment of BPGs for use of CFD codes, for judgement of CFD calculations and for assessment of experimental data; (ii) assessment of CFD simulations for three-dimensional flows in LWR primary systems and containments; (iii) quality-controlled CFD simulations for selected UPTF and SETH PANDA test cases; and (iv) demonstration of CFD code customisation for PTS analysis by implementation and validation of improved turbulence and two-phase flow models. The project started in October 2001 and is for a period of 36 months. The project consortium consists of 12 partners combining thermal-hydraulic experts, code developers, safety experts and engineers from nuclear industry and research organizations. At mid-term, the following results were achieved: (i) BPGs are available for simulations of reactor safety relevant flows. These BPGs have found interest in the European projects FLOMIX-R, ASTAR and ITEM; (ii) important flow phenomena for PTS and containment flows have been identified; (iii) experimental data featuring these phenomena have been selected and described in a standardised manner suitable for simulation with CFD methods; (iii) surveys of existing CFD calculations and experimental data for containment and primary loop flows have been performed and documented; (iv) first results for simulations of PTS-relevant single-phase and two-phase flow cases are available. Documentation is available via the internet at http://domino.grs.de/ecora/ecora.nsf. The models developed within the project are implemented in industrial and commercial CFD software packages and are therefore accessible by industry and research institutions.

    Original languageEnglish
    Pages (from-to)359 - 368
    Number of pages10
    JournalNuclear Engineering and Design
    Volume235
    Issue number2-4
    DOIs
    Publication statusPublished - 2005
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    reactor safety
    computational fluid dynamics
    Computational fluid dynamics
    evaluation
    containment
    simulation
    two phase flow
    Two phase flow
    industries
    method
    safety analysis
    Codes (standards)
    computer programs
    software
    research institution
    Nuclear industry
    three dimensional flow
    three-dimensional flow
    documentation
    industry

    Keywords

    • nuclear power plants
    • nuclear reactor safety
    • nuclear safety
    • validation
    • code validation
    • computational fluid dynamics
    • CFD
    • light water reactors

    Cite this

    Scheuerer, M., Heitsch, M., Menter, F., Egorov, Y., Toth, I., Bestion, D., ... Kimber, G. (2005). Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA). Nuclear Engineering and Design, 235(2-4), 359 - 368. https://doi.org/10.1016/j.nucengdes.2004.08.049
    Scheuerer, M. ; Heitsch, M. ; Menter, F. ; Egorov, Y. ; Toth, I. ; Bestion, D. ; Pigny, S. ; Paillere, H. ; Martin, A. ; Boucker, M. ; Krepper, E. ; Willemsen, S. ; Muhlbauer, P. ; Andreani, M. ; Smith, B. ; Karlsson, R. ; Henriksson, M. ; Hemstrom, B. ; Karppinen, Ismo ; Kimber, G. / Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA). In: Nuclear Engineering and Design. 2005 ; Vol. 235, No. 2-4. pp. 359 - 368.
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    abstract = "The objective of the ECORA project is the evaluation of computational fluid dynamics (CFD) software for reactor safety applications, resulting in best practice guidelines (BPG) for an efficient use of CFD for reactor safety problems. The project schedule is as follows: (i) establishment of BPGs for use of CFD codes, for judgement of CFD calculations and for assessment of experimental data; (ii) assessment of CFD simulations for three-dimensional flows in LWR primary systems and containments; (iii) quality-controlled CFD simulations for selected UPTF and SETH PANDA test cases; and (iv) demonstration of CFD code customisation for PTS analysis by implementation and validation of improved turbulence and two-phase flow models. The project started in October 2001 and is for a period of 36 months. The project consortium consists of 12 partners combining thermal-hydraulic experts, code developers, safety experts and engineers from nuclear industry and research organizations. At mid-term, the following results were achieved: (i) BPGs are available for simulations of reactor safety relevant flows. These BPGs have found interest in the European projects FLOMIX-R, ASTAR and ITEM; (ii) important flow phenomena for PTS and containment flows have been identified; (iii) experimental data featuring these phenomena have been selected and described in a standardised manner suitable for simulation with CFD methods; (iii) surveys of existing CFD calculations and experimental data for containment and primary loop flows have been performed and documented; (iv) first results for simulations of PTS-relevant single-phase and two-phase flow cases are available. Documentation is available via the internet at http://domino.grs.de/ecora/ecora.nsf. The models developed within the project are implemented in industrial and commercial CFD software packages and are therefore accessible by industry and research institutions.",
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    author = "M. Scheuerer and M. Heitsch and F. Menter and Y. Egorov and I. Toth and D. Bestion and S. Pigny and H. Paillere and A. Martin and M. Boucker and E. Krepper and S. Willemsen and P. Muhlbauer and M. Andreani and B. Smith and R. Karlsson and M. Henriksson and B. Hemstrom and Ismo Karppinen and G. Kimber",
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    Scheuerer, M, Heitsch, M, Menter, F, Egorov, Y, Toth, I, Bestion, D, Pigny, S, Paillere, H, Martin, A, Boucker, M, Krepper, E, Willemsen, S, Muhlbauer, P, Andreani, M, Smith, B, Karlsson, R, Henriksson, M, Hemstrom, B, Karppinen, I & Kimber, G 2005, 'Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA)', Nuclear Engineering and Design, vol. 235, no. 2-4, pp. 359 - 368. https://doi.org/10.1016/j.nucengdes.2004.08.049

    Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA). / Scheuerer, M. (Corresponding Author); Heitsch, M.; Menter, F.; Egorov, Y.; Toth, I.; Bestion, D.; Pigny, S.; Paillere, H.; Martin, A.; Boucker, M.; Krepper, E.; Willemsen, S.; Muhlbauer, P.; Andreani, M.; Smith, B.; Karlsson, R.; Henriksson, M.; Hemstrom, B.; Karppinen, Ismo; Kimber, G.

    In: Nuclear Engineering and Design, Vol. 235, No. 2-4, 2005, p. 359 - 368.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA)

    AU - Scheuerer, M.

    AU - Heitsch, M.

    AU - Menter, F.

    AU - Egorov, Y.

    AU - Toth, I.

    AU - Bestion, D.

    AU - Pigny, S.

    AU - Paillere, H.

    AU - Martin, A.

    AU - Boucker, M.

    AU - Krepper, E.

    AU - Willemsen, S.

    AU - Muhlbauer, P.

    AU - Andreani, M.

    AU - Smith, B.

    AU - Karlsson, R.

    AU - Henriksson, M.

    AU - Hemstrom, B.

    AU - Karppinen, Ismo

    AU - Kimber, G.

    PY - 2005

    Y1 - 2005

    N2 - The objective of the ECORA project is the evaluation of computational fluid dynamics (CFD) software for reactor safety applications, resulting in best practice guidelines (BPG) for an efficient use of CFD for reactor safety problems. The project schedule is as follows: (i) establishment of BPGs for use of CFD codes, for judgement of CFD calculations and for assessment of experimental data; (ii) assessment of CFD simulations for three-dimensional flows in LWR primary systems and containments; (iii) quality-controlled CFD simulations for selected UPTF and SETH PANDA test cases; and (iv) demonstration of CFD code customisation for PTS analysis by implementation and validation of improved turbulence and two-phase flow models. The project started in October 2001 and is for a period of 36 months. The project consortium consists of 12 partners combining thermal-hydraulic experts, code developers, safety experts and engineers from nuclear industry and research organizations. At mid-term, the following results were achieved: (i) BPGs are available for simulations of reactor safety relevant flows. These BPGs have found interest in the European projects FLOMIX-R, ASTAR and ITEM; (ii) important flow phenomena for PTS and containment flows have been identified; (iii) experimental data featuring these phenomena have been selected and described in a standardised manner suitable for simulation with CFD methods; (iii) surveys of existing CFD calculations and experimental data for containment and primary loop flows have been performed and documented; (iv) first results for simulations of PTS-relevant single-phase and two-phase flow cases are available. Documentation is available via the internet at http://domino.grs.de/ecora/ecora.nsf. The models developed within the project are implemented in industrial and commercial CFD software packages and are therefore accessible by industry and research institutions.

    AB - The objective of the ECORA project is the evaluation of computational fluid dynamics (CFD) software for reactor safety applications, resulting in best practice guidelines (BPG) for an efficient use of CFD for reactor safety problems. The project schedule is as follows: (i) establishment of BPGs for use of CFD codes, for judgement of CFD calculations and for assessment of experimental data; (ii) assessment of CFD simulations for three-dimensional flows in LWR primary systems and containments; (iii) quality-controlled CFD simulations for selected UPTF and SETH PANDA test cases; and (iv) demonstration of CFD code customisation for PTS analysis by implementation and validation of improved turbulence and two-phase flow models. The project started in October 2001 and is for a period of 36 months. The project consortium consists of 12 partners combining thermal-hydraulic experts, code developers, safety experts and engineers from nuclear industry and research organizations. At mid-term, the following results were achieved: (i) BPGs are available for simulations of reactor safety relevant flows. These BPGs have found interest in the European projects FLOMIX-R, ASTAR and ITEM; (ii) important flow phenomena for PTS and containment flows have been identified; (iii) experimental data featuring these phenomena have been selected and described in a standardised manner suitable for simulation with CFD methods; (iii) surveys of existing CFD calculations and experimental data for containment and primary loop flows have been performed and documented; (iv) first results for simulations of PTS-relevant single-phase and two-phase flow cases are available. Documentation is available via the internet at http://domino.grs.de/ecora/ecora.nsf. The models developed within the project are implemented in industrial and commercial CFD software packages and are therefore accessible by industry and research institutions.

    KW - nuclear power plants

    KW - nuclear reactor safety

    KW - nuclear safety

    KW - validation

    KW - code validation

    KW - computational fluid dynamics

    KW - CFD

    KW - light water reactors

    U2 - 10.1016/j.nucengdes.2004.08.049

    DO - 10.1016/j.nucengdes.2004.08.049

    M3 - Article

    VL - 235

    SP - 359

    EP - 368

    JO - Nuclear Engineering and Design

    JF - Nuclear Engineering and Design

    SN - 0029-5493

    IS - 2-4

    ER -