| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 6761167 | Nuclear Engineering and Design | 2015 | 12 Pages |
Abstract
Void fraction and pressure drops measurements in the BFBT bundle performed under steady-state and transient conditions which are representative for e.g. turbine trip and recirculation pump trip events, are compared with the numerical results of ATHLET. The comparison of code predictions with the BFBT data has shown good agreement given the experimental uncertainty and the results are consistent with the trends obtained with similar thermal-hydraulic codes.
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Authors
Valentino Di Marcello, Javier Jimenez Escalante, Victor Sanchez Espinoza,