Title:	Potential of serpent-openFOAM coupled codes for spent nuclear fuel analysis
Authors:	Kořínek, Tomáš Závorka, Jiří Lovecký, Martin Škoda, Radek
Citation:	KOŘÍNEK, T. ZÁVORKA, J. LOVECKÝ, M. ŠKODA, R. Potential of serpent-openFOAM coupled codes for spent nuclear fuel analysis. In Proceedings of the International Conference Nuclear Energy for New Europe (NENE 2021). Ljubljana: Nuclear Society of Slovenia, 2021. s. 613.1-613.8. ISBN: 978-961-6207-51-5
Issue Date:	2021
Publisher:	Nuclear Society of Slovenia
Document type:	konferenční příspěvek ConferenceObject
URI:	http://hdl.handle.net/11025/46766
ISBN:	978-961-6207-51-5
Keywords in different language:	multi-physics;Monte Carlo;CFD;serpent;OpenFOAM
Abstract in different language:	Operation of future district heating source Teplator with spent nuclear fuel assemblies requires deep analyses. The present article focus on a potential use of coupled neutronics and thermal-hydraulics codes for simulations with the spent fuel. The simulations were conducted in the neutronics code Serpent and the open-source CFD package OpenFOAM. Both codes were externally coupled operating at a prescribed number of loops. The goal of the study was to evaluate the influence of thermal-hydraulics (TH) feedback in investigation of the spent nuclear fuel. First coupling tests were conducted on a fuel pin of the VVER-440 fuel assembly. Results obtained from the coupled simulations showed a relatively small difference in the predicted heat power distribution between simulations with and without TH from OpenFOAM. Further, the greatest relative difference in coupled loops was between first two coupling loops with overall difference less than 3 % and the difference at the third loop was less than 0.1 %.
Rights:	Plný text je přístupný v rámci univerzity přihlášeným uživatelům. © Nuclear Society of Slovenia
Appears in Collections:	Konferenční příspěvky / Conference papers (RICE) OBD

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