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Importance of conjugate heat transfer modeling in transient CFD simulations
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0002-0683-9136
2019 (English)In: 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, American Nuclear Society , 2019, p. 615-626Conference paper, Published paper (Refereed)
Abstract [en]

Within the European SESAME project, system thermal-hydraulics (STH), computational fluid dynamics (CFD) and coupled 1D-3D thermal-hydraulic simulations are being carried out for Generation IV nuclear systems. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH participated in the project with activities related to the development and validation of CFD and coupled CFD-STH codes. The TALL-3D facility, operated by the KTH Royal Institute of Technology in Stockholm, is designed for thermal-hydraulic experiments with lead-bismuth eutectic (LBE) coolant. A well-instrumented, partially heated test section with cylindrical form is installed in the primary circuit. It is the domain of complex 3D flow and heat transfer phenomena. The CFD analyses showed that only the consideration of the fluid domain is not sufficient for correct prediction of the thermal-hydraulic transient dynamics. Therefore, solid structures like test section walls, inner circular plate, test section heater and even the insulation were explicitly included in the CFD model. This allowed the consideration in the simulations of the heat conduction and the thermal inertia of these components. The paper focuses on the analysis of the observed thermal-hydraulic flow phenomena during the TG03.S301.04 experiment and the comparison between ANSYS CFX predictions and data. Moreover, the influence of conjugate heat transfer (CHT) on the numerical results is investigated and discussed.

Place, publisher, year, edition, pages
American Nuclear Society , 2019. p. 615-626
Keywords [en]
CFD analysis, Experiment, Liquid metal, Solid structures, Transient simulation, Experiments, Heat conduction, Hydraulics, Liquid metals, Nuclear reactors, Storms, Two phase flow, Conjugate heat transfer, Lead-bismuth eutectics, Royal Institute of Technology, Thermal-hydraulic flow, Thermal-hydraulic simulations, Computational fluid dynamics
National Category
Physical Sciences
Identifiers
URN: urn:nbn:se:kth:diva-268605Scopus ID: 2-s2.0-85073741188OAI: oai:DiVA.org:kth-268605DiVA, id: diva2:1428374
Conference
18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 18 August 2019 through 23 August 2019
Note

QC 20200505

Available from: 2020-05-05 Created: 2020-05-05 Last updated: 2020-05-05Bibliographically approved

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Grishchenko, DmitryKudinov, Pavel

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