Full metadata record
| DC pole | Hodnota | Jazyk |
|---|---|---|
| dc.contributor.author | Kořínek, Tomáš | |
| dc.contributor.author | Závorka, Jiří | |
| dc.contributor.author | Lovecký, Martin | |
| dc.contributor.author | Škoda, Radek | |
| dc.date.accessioned | 2022-02-07T11:00:15Z | - |
| dc.date.available | 2022-02-07T11:00:15Z | - |
| dc.date.issued | 2021 | |
| dc.identifier.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 | cs |
| dc.identifier.isbn | 978-961-6207-51-5 | |
| dc.identifier.uri | http://hdl.handle.net/11025/46766 | |
| dc.format | 8 s. | cs |
| dc.format.mimetype | application/pdf | |
| dc.language.iso | en | en |
| dc.publisher | Nuclear Society of Slovenia | en |
| dc.relation.ispartofseries | Proceedings of the International Conference Nuclear Energy for New Europe (NENE 2021) | en |
| dc.rights | Plný text je přístupný v rámci univerzity přihlášeným uživatelům. | cs |
| dc.rights | © Nuclear Society of Slovenia | en |
| dc.title | Potential of serpent-openFOAM coupled codes for spent nuclear fuel analysis | en |
| dc.type | konferenční příspěvek | cs |
| dc.type | ConferenceObject | en |
| dc.rights.access | restrictedAccess | en |
| dc.type.version | publishedVersion | en |
| dc.description.abstract-translated | 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 %. | en |
| dc.subject.translated | multi-physics | en |
| dc.subject.translated | Monte Carlo | en |
| dc.subject.translated | CFD | en |
| dc.subject.translated | serpent | en |
| dc.subject.translated | OpenFOAM | en |
| dc.type.status | Peer-reviewed | en |
| dc.identifier.obd | 43934777 | |
| dc.project.ID | TK03030109/Vývoj technologického celku pro inovativní ukládání energií s využitím fázové změny materiálu | cs |
| dc.project.ID | LM2018131/Česká národní infrastruktura pro biologická data (ELIXIR-CZ) | cs |
| Vyskytuje se v kolekcích: | Konferenční příspěvky / Conference papers (RICE) OBD | |
Soubory připojené k záznamu:
| Soubor | Velikost | Formát | |
|---|---|---|---|
| Korinek_NENE2021_613.pdf | 827,7 kB | Adobe PDF | Zobrazit/otevřít Vyžádat kopii |
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