Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes

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Science and Technology of Nuclear Installations
Pages: 
20
Volume: 
2012
Date: 
Friday, July 20, 2012
DOI: 
http://dx.doi.org/10.1155/2012/746467

In order to assess the accuracy and validity of subchannel, system, and computational fluid dynamics codes, the Paul Scherrer
Institut has participated in the OECD/NRC PSBT benchmark with the thermal-hydraulic system code TRACE5.0 developed by
US NRC, the subchannel code FLICA4 developed by CEA, and the computational fluid dynamic code STAR-CD developed by
CD-adapco. The PSBT benchmark consists of a series of void distribution exercises and departure from nucleate boiling exercises.
The results reveal that the prediction by the subchannel code FLICA4 agrees with the experimental data reasonably well in both
steady-state and transient conditions. The analyses of single-subchannel experiments by means of the computational fluid dynamic
code STAR-CD with the CD-adapco boiling model indicate that the prediction of the void fraction has no significant discrepancy
from the experiments. The analyses with TRACE point out the necessity to performadditional assessment of the subcooled boiling
model and bulk condensation model of TRACE

Rights: 
2012 Taewan Kim et al
Author Name: 
Taewan Kim
Victor Petrov
Annalisa Manera
Simon Lo
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