Simulation of Subcooled Boiling in Multiphase CFD Code CFX
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F19%3A00338803" target="_blank" >RIV/68407700:21220/19:00338803 - isvavai.cz</a>
Výsledek na webu
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DOI - Digital Object Identifier
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Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Simulation of Subcooled Boiling in Multiphase CFD Code CFX
Popis výsledku v původním jazyce
This paper presents a validation of multiphase Computational Fluid Dynamics (CFD) code Ansys CFX 18 on selected experiments with the subcooled boiling flow. Ansys CFX code can simulate multiphase flow by solving three balance equations for each phase (Euler-Euler approach). Boiling on the heated wall can be simulated with the model proposed by Kurul and Podowski. A set of mathematical models of physical phenomena in boiling bubbly flow was selected and tested on the following experiments with subcooled boiling: DEBORA experiments, ASU experiments, FRIGG FT-6a experiment, and Bartolomej et al. experiment. The DEBORA experiment is a vertical pipe with a heated wall. The working fluid is freon R-12. The ASU boiling experiment is a vertical annular channel with a heated inner wall and freon R-113. The FRIGG FT-6a experiment is a vertical channel with 6 heated rods and boiling water. The Bartolomej experiment is a vertical heated pipe with boiling water. It was found out that CFX code can reasonably reproduce measured data in all these experiments. At the end of this paper, we present an application of this modeling approach to the real case with a complicated geometry: simulation of subcooled boiling in the VVER-1000 fuel assembly with bent rods.
Název v anglickém jazyce
Simulation of Subcooled Boiling in Multiphase CFD Code CFX
Popis výsledku anglicky
This paper presents a validation of multiphase Computational Fluid Dynamics (CFD) code Ansys CFX 18 on selected experiments with the subcooled boiling flow. Ansys CFX code can simulate multiphase flow by solving three balance equations for each phase (Euler-Euler approach). Boiling on the heated wall can be simulated with the model proposed by Kurul and Podowski. A set of mathematical models of physical phenomena in boiling bubbly flow was selected and tested on the following experiments with subcooled boiling: DEBORA experiments, ASU experiments, FRIGG FT-6a experiment, and Bartolomej et al. experiment. The DEBORA experiment is a vertical pipe with a heated wall. The working fluid is freon R-12. The ASU boiling experiment is a vertical annular channel with a heated inner wall and freon R-113. The FRIGG FT-6a experiment is a vertical channel with 6 heated rods and boiling water. The Bartolomej experiment is a vertical heated pipe with boiling water. It was found out that CFX code can reasonably reproduce measured data in all these experiments. At the end of this paper, we present an application of this modeling approach to the real case with a complicated geometry: simulation of subcooled boiling in the VVER-1000 fuel assembly with bent rods.
Klasifikace
Druh
D - Stať ve sborníku
CEP obor
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OECD FORD obor
20303 - Thermodynamics
Návaznosti výsledku
Projekt
<a href="/cs/project/TH02020360" target="_blank" >TH02020360: Modelování vzniku CHF - krize varu pomocí výpočetních programů typu CFD</a><br>
Návaznosti
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Ostatní
Rok uplatnění
2019
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Údaje specifické pro druh výsledku
Název statě ve sborníku
Proceedings of the 29th Symposium of AER on VVER Reactor Physics and Reactor Safety
ISBN
978-963-7351-32-7
ISSN
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e-ISSN
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Počet stran výsledku
17
Strana od-do
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Název nakladatele
Atomic Energy Research
Místo vydání
Budapest
Místo konání akce
Mochovce
Datum konání akce
14. 10. 2019
Typ akce podle státní příslušnosti
WRD - Celosvětová akce
Kód UT WoS článku
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