Validation of natural convection liquid metal flow in the E-SCAPE facility

Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review


Institutes & Expert groups

  • VKI - The Von Karman Institute for Fluid Dynamics

Documents & links


The work presented focuses on the reproduction of natural convection scenarios in the E-SCAPE facility with CFD. ESCAPE is a 1/6th scale model of the MYRRHA reactor with an electric core simulator. The pool of E-SCAPE has a diameter of 1.38m, while the core modelled by electrical resistance has details of less than a millimeter. Thus, E-SCAPE has similar scale separation features as a nuclear reactor and provides valuable experimental data to validate CFD tools for liquid metal pool-type reactors. The current work aims at capturing 3D effects as stratification and natural circulation in large plena with CFD. Given the inseparable connection between thermal and momentum field in natural convection, capturing such flows is particularly difficult with RANS modeling. Special attention is given to study the effect of modeling of turbulent heat transfer in liquid metal flows. A direct comparison is given with E-SCAPE experiments. Finally, the flow and thermal field predicted by CFD is compared in the E-SCAPE facility and the MYRRHA nuclear reactor. This first qualitative results of CFD indicates that the scaling of the E-SCAPE facility is allowing to reproduce the natural convection flow expected in the full-scale MYRRHA nuclear reactor during the passive cooling of the core decay heat.


Original languageEnglish
Title of host publicationThe 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19)
PublisherSCK CEN
Number of pages13
ISBN (Electronic)9789076971261
Publication statusPublished - 6 Mar 2022
Event2022 - NURETH - 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics - Brussels, Belgium
Duration: 6 Mar 202211 Mar 2022
Conference number: NURETH19


Conference2022 - NURETH - 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
Internet address


  • Liquid metal reactors, Pool type reactors, Low prandtl, Natural convection

ID: 7536339