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Science and Technology of Nuclear Installations
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Science and Technology of Nuclear Installations
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2014
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Article
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Tab 3
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Research Article
Validation of NEPTUNE-CFD Two-Phase Flow Models Using Experimental Data
Table 3
Results for the local and averaged VF for the different meshes applied for the simulation of case 1.2211.
Mesh
Nearest heated wall cell VF (%)
Average VF (%) at measured cross section (
m)
M1
67
8.1
M2
57
6.7
M3
40
4.6
M4
15
3.1