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

43 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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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 -