TY - GEN
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, Lila
N1 - Score=3
PY - 2019/3/19
Y1 - 2019/3/19
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 modeling 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 on flow and heat transport in the E-SCAPE pool are 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 modeling 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 on flow and heat transport in the E-SCAPE pool are presented and where possible validated against experimental results.
KW - MYRRHA
KW - CFD
KW - E-SCAPE
KW - LBE
KW - thermal hydraulics
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/35085249
UR - https://www.google.be/url?sa=t&rct=j&q=&esrc=s&source=web&cd=1&cad=rja&uact=8&ved=2ahUKEwisqcW8gabnAhWKZMAKHQ6fBAsQFjAAegQIARAB&url=http%3A%2F%2Fsesame-h2020.eu%2Fwp-content%2Fuploads%2F2015%2F08%2F190121-SESAME-Workshop-Program.pdf&usg=AOvVaw30M4K4lDtHw1qwf-C_r8db
M3 - In-proceedings paper
SP - 1
EP - 9
BT - SESAME International Workshop
PB - Unknown
T2 - SESAME International Workshop
Y2 - 19 March 2019 through 21 March 2019
ER -