Benchmark of Subchannel Code VIPRE-W with PSBT Void and Temperature Test Data

This paper summarizes comparisons of VIPRE-W thermal-hydraulic subchannel code predictions with measurements of fluid temperature and void from pressurized water reactor subchannel and bundle tests. Using an existing turbulent mixing model, the empirical coefficient derived from code predictions in...

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Bibliographic Details
Published in:Science and technology of nuclear installations 2012-01, Vol.2012 (2012), p.1-11
Main Authors: Sung, Y., Oelrich, R. L., Lee, C. C., Ruiz-Esquide, N., Gambetta, M., Mazufri, C. M.
Format: Article
Language:English
Subjects:
Bundling
Cold
Computational fluid dynamics
Design
Fluid flow
Fluids
Mathematical models
Measurement techniques
Nuclear fuels
Nuclear reactors
Studies
Temperature
Turbulence
Turbulent flow
Voids
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Summary:This paper summarizes comparisons of VIPRE-W thermal-hydraulic subchannel code predictions with measurements of fluid temperature and void from pressurized water reactor subchannel and bundle tests. Using an existing turbulent mixing model, the empirical coefficient derived from code predictions in comparison to the fluid temperature measurement is similar to those from previous mixing tests of similar bundle configurations. The predicted steady-state axial void distributions and time-dependent void profiles based on the Lellouche and Zolotar model generally agree well with the test data. The void model tends to predict lower void at the upper elevation under bulk boiling. The void predictions are in closer agreement with the measurements from the power increase, temperature increase, and flow reduction transients than the depressurization transient. Additional model sensitivity studies showed no significant improvement in the code predictions as compared to the published test data.
ISSN:1687-6075
1687-6083
DOI:10.1155/2012/757498