CFD analyses of the European scaled pool experiment E-SCAPE

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CFD analyses of the European scaled pool experiment E-SCAPE. / Visser, Dirk; Keijers, Steven; Lopes, Silvania; Roelofs, Ferry; Van Tichelen, Katrien; Koloszar, Lilla.

In: Nuclear Engineering and Design, Vol. 358, 110436, 01.03.2020.

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Harvard

Visser, D, Keijers, S, Lopes, S, Roelofs, F, Van Tichelen, K & Koloszar, L 2020, 'CFD analyses of the European scaled pool experiment E-SCAPE', Nuclear Engineering and Design, vol. 358, 110436. https://doi.org/10.1016/j.nucengdes.2019.110436

APA

Visser, D., Keijers, S., Lopes, S., Roelofs, F., Van Tichelen, K., & Koloszar, L. (2020). CFD analyses of the European scaled pool experiment E-SCAPE. Nuclear Engineering and Design, 358, [110436]. https://doi.org/10.1016/j.nucengdes.2019.110436

Vancouver

Visser D, Keijers S, Lopes S, Roelofs F, Van Tichelen K, Koloszar L. CFD analyses of the European scaled pool experiment E-SCAPE. Nuclear Engineering and Design. 2020 Mar 1;358. 110436. https://doi.org/10.1016/j.nucengdes.2019.110436

Author

Visser, Dirk ; Keijers, Steven ; Lopes, Silvania ; Roelofs, Ferry ; Van Tichelen, Katrien ; Koloszar, Lilla. / CFD analyses of the European scaled pool experiment E-SCAPE. In: Nuclear Engineering and Design. 2020 ; Vol. 358.

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@article{f0fdf2982d344ed39f83d1b03ac20953,
title = "CFD analyses of the European scaled pool experiment E-SCAPE",
abstract = "The European Scaled Pool Experiment (E-SCAPE) is a 1/6th-scale thermal hydraulic model of the MYRRHA reactor and has been developed within the European framework programs THINS and MYRTE. MYRRHA is a multi-purpose hybrid pool-type research reactor cooled with lead-bismuth eutectic (LBE) that is under design at the Belgian nuclear research center SCK•CEN. The experiments from the E-SCAPE facility are essential for the design and licensing of MYRRHA. On the one hand, the experimental data from E-SCAPE directly provide information to the designers on the flow patterns and heat transport in the LBE in the upper and lower plena of the reactor. On the other hand, the experimental data from E-SCAPE enable qualification of thermal hydraulic computer codes used for analyzing the flow and heat transport in the MYRRHA reactor. The accuracy of codes rely on the underlying modelling approaches, whose validity can only be assessed by comparing them with relevant experimental data. Given the rare conditions present in heavy liquid cooled nuclear reactors, the possibility to compare complete pool simulations with experimental data is a unique opportunity. This paper presents the modelling approaches and first results of the pre-test analyses performed for E-SCAPE by NRG, SCK•CEN and VKI using Computational Fluid Dynamics (CFD). The CFD analyses of NRG are performed with the STAR-CCM+code, at SCK•CEN with the ANSYS CFX code and at VKI OpenFOAM is used. A first comparison of the results obtained with three different CFD codes for flow and heat transport in the E-SCAPE pool is presented and, where possible, validated against experimental results.",
keywords = "E-SCAPE, CFD, thermal hydraulics, pool",
author = "Dirk Visser and Steven Keijers and Silvania Lopes and Ferry Roelofs and {Van Tichelen}, Katrien and Lilla Koloszar",
note = "Score=10",
year = "2020",
month = "3",
day = "1",
doi = "10.1016/j.nucengdes.2019.110436",
language = "English",
volume = "358",
journal = "Nuclear Engineering and Design",
issn = "0029-5493",
publisher = "Elsevier",

}

RIS - Download

TY - JOUR

T1 - CFD analyses of the European scaled pool experiment E-SCAPE

AU - Visser, Dirk

AU - Keijers, Steven

AU - Lopes, Silvania

AU - Roelofs, Ferry

AU - Van Tichelen, Katrien

AU - Koloszar, Lilla

N1 - Score=10

PY - 2020/3/1

Y1 - 2020/3/1

N2 - The European Scaled Pool Experiment (E-SCAPE) is a 1/6th-scale thermal hydraulic model of the MYRRHA reactor and has been developed within the European framework programs THINS and MYRTE. MYRRHA is a multi-purpose hybrid pool-type research reactor cooled with lead-bismuth eutectic (LBE) that is under design at the Belgian nuclear research center SCK•CEN. The experiments from the E-SCAPE facility are essential for the design and licensing of MYRRHA. On the one hand, the experimental data from E-SCAPE directly provide information to the designers on the flow patterns and heat transport in the LBE in the upper and lower plena of the reactor. On the other hand, the experimental data from E-SCAPE enable qualification of thermal hydraulic computer codes used for analyzing the flow and heat transport in the MYRRHA reactor. The accuracy of codes rely on the underlying modelling approaches, whose validity can only be assessed by comparing them with relevant experimental data. Given the rare conditions present in heavy liquid cooled nuclear reactors, the possibility to compare complete pool simulations with experimental data is a unique opportunity. This paper presents the modelling approaches and first results of the pre-test analyses performed for E-SCAPE by NRG, SCK•CEN and VKI using Computational Fluid Dynamics (CFD). The CFD analyses of NRG are performed with the STAR-CCM+code, at SCK•CEN with the ANSYS CFX code and at VKI OpenFOAM is used. A first comparison of the results obtained with three different CFD codes for flow and heat transport in the E-SCAPE pool is presented and, where possible, validated against experimental results.

AB - The European Scaled Pool Experiment (E-SCAPE) is a 1/6th-scale thermal hydraulic model of the MYRRHA reactor and has been developed within the European framework programs THINS and MYRTE. MYRRHA is a multi-purpose hybrid pool-type research reactor cooled with lead-bismuth eutectic (LBE) that is under design at the Belgian nuclear research center SCK•CEN. The experiments from the E-SCAPE facility are essential for the design and licensing of MYRRHA. On the one hand, the experimental data from E-SCAPE directly provide information to the designers on the flow patterns and heat transport in the LBE in the upper and lower plena of the reactor. On the other hand, the experimental data from E-SCAPE enable qualification of thermal hydraulic computer codes used for analyzing the flow and heat transport in the MYRRHA reactor. The accuracy of codes rely on the underlying modelling approaches, whose validity can only be assessed by comparing them with relevant experimental data. Given the rare conditions present in heavy liquid cooled nuclear reactors, the possibility to compare complete pool simulations with experimental data is a unique opportunity. This paper presents the modelling approaches and first results of the pre-test analyses performed for E-SCAPE by NRG, SCK•CEN and VKI using Computational Fluid Dynamics (CFD). The CFD analyses of NRG are performed with the STAR-CCM+code, at SCK•CEN with the ANSYS CFX code and at VKI OpenFOAM is used. A first comparison of the results obtained with three different CFD codes for flow and heat transport in the E-SCAPE pool is presented and, where possible, validated against experimental results.

KW - E-SCAPE

KW - CFD

KW - thermal hydraulics

KW - pool

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/37001685

U2 - 10.1016/j.nucengdes.2019.110436

DO - 10.1016/j.nucengdes.2019.110436

M3 - Article

VL - 358

JO - Nuclear Engineering and Design

JF - Nuclear Engineering and Design

SN - 0029-5493

M1 - 110436

ER -

ID: 5988084