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Simulation of Subcooled Boiling in Multiphase CFD Code CFX

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F19%3AN0000045" target="_blank" >RIV/46356088:_____/19:N0000045 - isvavai.cz</a>

  • Result on the web

  • DOI - Digital Object Identifier

Alternative languages

  • Result language

    angličtina

  • Original language name

    Simulation of Subcooled Boiling in Multiphase CFD Code CFX

  • Original language description

    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. Presented at the 29th Symposium of AER on VVER Reactor Physics and Reactor Safety, At Energoland Mochovce, NPP Mochovce, Slovakia.

  • Czech name

  • Czech description

Classification

  • Type

    O - Miscellaneous

  • CEP classification

  • OECD FORD branch

    20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Result continuities

  • Project

    <a href="/en/project/TH02020360" target="_blank" >TH02020360: Modeling of CHF-boiling crisis by using CFD computer codes</a><br>

  • Continuities

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

Others

  • Publication year

    2019

  • Confidentiality

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