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Multiphase Science and Technology

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ISSN Imprimer: 0276-1459

ISSN En ligne: 1943-6181

SJR: 0.144 SNIP: 0.256 CiteScore™:: 1.1 H-Index: 24

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DELAYED EQUILIBRIUM MODEL (DEM) OF FLASHING CHOKED FLOWS RELEVANT TO LOCA

Volume 25, Numéro 2-4, 2013, pp. 117-131
DOI: 10.1615/MultScienTechn.v25.i2-4.50
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RÉSUMÉ

In the context of nuclear reactor safety, a pipe breach in the primary circuit is the initiator of a loss of coolant accident (LOCA). The calculation of leak rates involving the discharge of water and steam mixtures plays an important role in the modeling of LOCAs for both generation (GEN) II and GEN III reactors, and also for the supercritical water reactor of GEN IV. Indeed, the flow though the breach determines the depressurization rate of the system and the time to core uncover, which in turn are of major concern for when and how different mitigation auxiliary systems will be initiated and efficient. This paper deals with the delayed equilibrium model (DEM), which focuses on thermodynamic non-equilibrium conditions that prevail in the flashing flow process near the critical section. The DEM developed at the University of Louvain is a one-dimensional model for the choked or critical flow rate in steady-state or quasi-steady-state conditions, which deals with the effect of the metastable liquid phase during the flashing process. The DEM has been compared with 500 experimental data. The DEM was recently assessed against the Super-Mobydick and Bethsy experiments done at the Commissariat a L'Energie Atomique during the 1980s.

CITÉ PAR
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  2. Nouri-Borujerdi A., Shafiei Ghazani A., A non-equilibrium relaxation model for fast depressurization of pipelines, Annals of Nuclear Energy, 111, 2018. Crossref

  3. De Lorenzo M., Lafon Ph., Seynhaeve J.-M., Bartosiewicz Y., Benchmark of Delayed Equilibrium Model (DEM) and classic two-phase critical flow models against experimental data, International Journal of Multiphase Flow, 92, 2017. Crossref

  4. Zhang J., Wang M.J., Zhang Z., Sun H., Wu Y.W., Tian W.X., Qiu S.Z., Su G.H., A comprehensive review of the leak flow through micro-cracks (in LBB) for nuclear system: Morphologies and thermal-hydraulic characteristics, Nuclear Engineering and Design, 362, 2020. Crossref

  5. Ringstad Knut Emil, Allouche Yosr, Gullo Paride, Ervik Åsmund, Banasiak Krzysztof, Hafner Armin, A detailed review on CO2 two-phase ejector flow modeling, Thermal Science and Engineering Progress, 20, 2020. Crossref

  6. Xu Hong, Badea Aurelian Florin, Cheng Xu, Studies on the criterion for choking process in two-phase flow, Progress in Nuclear Energy, 133, 2021. Crossref

  7. Ferrando Marco, Renuke Avinash, Traverso Alberto, Sishtla Vishnu, A new design method for two-phase nozzles in high efficiency heat pumps, International Journal of Refrigeration, 127, 2021. Crossref

  8. Fang Yu, De Lorenzo Marco, Lafon Philippe, Poncet Sébastien, Bartosiewicz Yann, An Accurate and Efficient Look-up Table Equation of State for Two-Phase Compressible Flow Simulations of Carbon Dioxide, Industrial & Engineering Chemistry Research, 57, 22, 2018. Crossref

  9. Yin Songtao, Zhu Mengxin, Liu Qihang, Wang Haijun, Two-phase modeling of micro-channel critical flows with inlet sub-cooling: A review and benchmark study, International Journal of Thermal Sciences, 179, 2022. Crossref

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