Comparisons of the RALIZA-2/02 two-phase flow model with experimental data |
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Authors: | N.I. Kolev |
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Affiliation: | Institute for Nuclear Research and Nuclear Energy, Boul. Lenin 72, Sofia 1113, Bulgaria |
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Abstract: | The RALIZA-2 computer program was designed for thermal-hydraulic analysis of flow channel and fuel element of PWR/BWR at steady-state and transient conditions. A nonhomogeneous, nonequilibrium model of a two-phase flow and a two-dimensional heat conduction model of fuel pin are used in the program. A fully implicit integration scheme for both models is used. The steady-state constitutive correlations set is used. The void fraction, pre- and post-DNB heat transfer mechanism are compared with data. Also a loss of flow experiment was calculated and compared with nuclear heated rod bundle experimental data for typical PWRs. A very good agreement was obtained. |
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