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Validation of a thermo-fluid-structure coupling approach for RPV creep failure analysis against FOREVER-EC2 experiment
KTH, Skolan för teknikvetenskap (SCI), Fysik, Kärnkraftssäkerhet.ORCID-id: 0000-0003-0408-8807
KTH, Skolan för teknikvetenskap (SCI), Fysik, Kärnkraftssäkerhet. Royal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, Sweden..
KTH, Skolan för teknikvetenskap (SCI), Fysik, Kärnkraftssäkerhet.ORCID-id: 0000-0003-3132-7252
KTH, Skolan för teknikvetenskap (SCI), Fysik, Kärnkraftssäkerhet.
Vise andre og tillknytning
2019 (engelsk)Inngår i: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 133, s. 637-648Artikkel i tidsskrift (Fagfellevurdert) Published
Abstract [en]

The failure of reactor pressure vessel (RPV) during a severe accident of light water reactors is a thermal fluid-structure interaction (FSI) problem which involves melt pool heat transfer and creep deformation of the RPV. The present study is intended to explore a reliable coupling approach of thermo-fluid-structure analyses which will not only be able to reflect the transient thermal FSI feature, but also apply the advanced models and computational platforms to melt pool convection and structural mechanics, so as to improve simulation fidelity. For this purpose, the multi-physics platform of ANSYS encompassing Fluent and Structural capabilities was employed to simulate the fluid dynamics and structural mechanics in a coupled manner. In particular, the FOREVER-EC2 experiment was chosen to validate the coupling approach. The natural convection in melt pool was modeled with the SST turbulence model with a well-resolved boundary layer, while the creep deformation for the vessel made of 16MND5 steel was analyzed with a new three-stage creep model (modified theta projection model). A utility tool was introduced to transfer the transient thermal loads from Fluent to Structural which minimizes the user effort in performing the coupled analysis. The validation work demonstrated the well-posed capability of the coupling approach for prediction of the key parameters of interest, including temperature profile, total displacement of vessel bottom point and the evolution of wall thickness profile in the experiment. Ltd. All rights reserved.

sted, utgiver, år, opplag, sider
PERGAMON-ELSEVIER SCIENCE LTD , 2019. Vol. 133, s. 637-648
Emneord [en]
Reactor pressure vessel, Creep failure, Thermal fluid-structure interaction, Computational fluid dynamics, Computational structural mechanics, Coupled analysis
HSV kategori
Forskningsprogram
Energiteknik; Energiteknik
Identifikatorer
URN: urn:nbn:se:kth:diva-260983DOI: 10.1016/j.anucene.2019.06.067ISI: 000484649800061Scopus ID: 2-s2.0-85068784394OAI: oai:DiVA.org:kth-260983DiVA, id: diva2:1359770
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QC 20191010

Tilgjengelig fra: 2019-10-10 Laget: 2019-10-10 Sist oppdatert: 2019-11-26bibliografisk kontrollert

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Yu, PengMa, WeiminVillanueva, WalterKarbojian, AramBechta, Sevostian

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