Experimental and Numerical Characterization of the Flow Field at the Core Entrance of a Water Model of a Heavy Liquid Metal–Cooled Reactor

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Institutes & Expert groups

  • VKI - The Von Karman Institute for Fluid Dynamics

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Abstract

The thermal-hydraulic challenges of a nuclear reactor are numerous and mastering them is crucial for the design and safety of new reactors. Numerical simulation through computational fluid dynamics (CFD) codes or system thermal-hydraulic codes can address a lot of the different questions, nevertheless the use of water modeling for the study of the thermal-hydraulic behavior of a new primary system and the validation of codes remains an extremely valuable tool. A water model of the pool-type PbBi-cooled MYRRHA reactor has been developed at the von Karman Institute in collaboration with SCK•CEN. It is a full plexiglass model at a geometrical scale 1/5 of MYRRHA. This transparent water model allows the application of optical measurement techniques like particle image velocimetry (PIV) for flow characterization. Local results of PIV measurements performed in the lower plenum at the entrance of the core are presented and compared with CFD results for nominal operating condition and a natural convection case simulating decay heat removal. Very good agreement has been found in the velocity field. The results also show the importance of the radial flow entering the core of the water model in natural convection.

Details

Original languageEnglish
Pages (from-to)231-241
Number of pages11
JournalNuclear Technology
Volume206
Issue number2
DOIs
Publication statusPublished - Feb 2020
Event2018 - ATH - Advances in Thermal Hydraulics meeting - Orlando, United States
Duration: 11 Nov 201815 Nov 2018

Keywords

  • MYRRHA, water model, particle image velocimetry, computational fluid dynamics, validation

ID: 5973940