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Published in 2021 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2021.111185
Abstract: Abstract The two-fluid model has been adopted as a platform of nuclear thermal–hydraulic system analysis code because it can treat the mechanical and thermal non-equilibrium between phases through the interfacial transfer terms. Precise modeling of…
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Keywords:
two phase;
drag force;
interfacial drag;
drift flux ... See more keywords
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Published in 2019 at "Journal of Nuclear Science and Technology"
DOI: 10.1080/00223131.2019.1617203
Abstract: ABSTRACT Accurate prediction of interfacial drag in the downcomer annulus is crucial for the assessment of downcomer void fraction for the loss of coolant accident analysis. The downcomer annulus is the gap between reactor pressure…
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Keywords:
void fraction;
drift flux;
downcomer;
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Published in 2024 at "Nuclear Technology"
DOI: 10.1080/00295450.2024.2370189
Abstract: Abstract The advanced thermal-hydraulic system code, System Analysis Module (SAM), was originally developed for the modeling of single-phase flow in advanced reactors. It has since been expanded to include a four-equation drift flux model for…
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Keywords:
drift flux;
verification;
model;
gas ... See more keywords
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Published in 2020 at "Fluids"
DOI: 10.3390/fluids5010031
Abstract: The continuous adjoint approach is a technique for calculating the sensitivity of a flow to changes in input parameters, most commonly changes of geometry. Here we present for the first time the mathematical derivation of…
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Keywords:
multiphase flow;
derivation adjoint;
adjoint;
drift flux ... See more keywords
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Published in 2024 at "Physicochemical Problems of Mineral Processing"
DOI: 10.37190/ppmp/178234
Abstract: This communication presents a methodology, based on a modified drift flux model, to determine bubble size distribution in column flotation. The modified drift flux model incorporates a surfactant-type parameter. This parameter considers the impact of…
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Keywords:
methodology;
type;
drift flux;
bubble size ... See more keywords