2020
DOI: 10.1016/j.nucengdes.2020.110827
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Thermal-hydraulic validation of two-phase models in THUNDER code against benchmark results and CFD codes

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Cited by 2 publications
(1 citation statement)
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“…Various subchannel codes and CFD codes have been proposed to analyze the gas–liquid phase change in nuclear reactors. The simulation of industrial nuclear reactors is often carried out by subchannel codes, such as COBRA, SUBCHANFLOW, and THUNDER. , Despite their computational efficiency, the subchannel codes greatly rely on empirical correlation. Many micro/meso scale details are lost during subchannel code simulations .…”
Section: Phase Change For Thermal Management (Tm)mentioning
confidence: 99%
“…Various subchannel codes and CFD codes have been proposed to analyze the gas–liquid phase change in nuclear reactors. The simulation of industrial nuclear reactors is often carried out by subchannel codes, such as COBRA, SUBCHANFLOW, and THUNDER. , Despite their computational efficiency, the subchannel codes greatly rely on empirical correlation. Many micro/meso scale details are lost during subchannel code simulations .…”
Section: Phase Change For Thermal Management (Tm)mentioning
confidence: 99%