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Multiscale analysis of forced and natural convection including heat transfer phenomena in the tall-3D experimental facility
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2015 (English)In: International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, American Nuclear Society, 2015, Vol. 4, 2917-2930 p.Conference paper (Refereed)Text
Abstract [en]

Within the European FP7 project THINS (Thermal Hydraulics of Innovative Nuclear Systems), numerical tools for the simulation of the thermal-hydraulics of next generation rector systems were developed, applied and validated for innovative coolants. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, the Technische Universitaet Muenchen (TUM) and the Royal Institute of Technology (KTH) participated in THINS activities related to the development and validation of computational fluid dynamics (CFD), System Thermal Hydraulics (STH) and coupled STH - CFD codes. High quality measurements from the experiments performed at the TALL-3D facility, operated by KTH, were used to assess the numerical results. This paper summarizes the work accomplished for the validation of the coupled codes ATHLET-ANSYS CFX and RELAP5/STAR CCM+ and highlights the main results achieved for the T01.09 experiment.

Place, publisher, year, edition, pages
American Nuclear Society, 2015. Vol. 4, 2917-2930 p.
Keyword [en]
Coupled codes, Innovative reactors, Validation
National Category
Other Engineering and Technologies not elsewhere specified
Identifiers
URN: urn:nbn:se:kth:diva-187413ScopusID: 2-s2.0-84962691876ISBN: 978-151081184-3OAI: oai:DiVA.org:kth-187413DiVA: diva2:930658
Conference
16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015; Chicago
Note

20160525

Available from: 2016-05-25 Created: 2016-05-23 Last updated: 2016-05-25Bibliographically approved

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Grischenko, Dmitry
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Nuclear Power Safety
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