Potential of Serpent-OpenFOAM Coupled Codes for Spent Nuclear Fuel Analysis

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21730%2F21%3A00356964" target="_blank" >RIV/68407700:21730/21:00356964 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/49777513:23220/21:43963778

Výsledek na webu

<a href="https://www.djs.si/nene2021/proceedings/pdf/NENE2021_613.pdf" target="_blank" >https://www.djs.si/nene2021/proceedings/pdf/NENE2021_613.pdf</a>

DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Potential of Serpent-OpenFOAM Coupled Codes for Spent Nuclear Fuel Analysis

Popis výsledku v původním jazyce

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 %

Název v anglickém jazyce

Potential of Serpent-OpenFOAM Coupled Codes for Spent Nuclear Fuel Analysis

Popis výsledku anglicky

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 %

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

10304 - Nuclear physics

Projekt

<a href="/cs/project/TK03030109" target="_blank" >TK03030109: Vývoj technologického celku pro inovativní ukládání energií s využitím fázové změny materiálu</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2021

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název statě ve sborníku

Proceedings - 30th International Conference Nuclear Energy for New Europe - NENE 2021

ISBN

978-961-6207-51-5

ISSN

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e-ISSN

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Počet stran výsledku

8

Strana od-do

484-491

Název nakladatele

Nuclear Society of Slovenia

Místo vydání

Ljubljana

Místo konání akce

Bled

Datum konání akce

6. 9. 2021

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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