Development of a drift-flux model based core thermal-hydraulics code for efficient high-fidelity multiphysics calculation

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ID: 54763
2019
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lee2019developmentnuclear Use this key to autocite in the manuscript while using SciMatic Manuscript Manager or Thesis Manager
Authors Lee, J.
Journal nuclear engineering and technology
Year 2019
DOI
10.1016/j.net.2019.04.002
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