Affiliation:
1. Forsmark Nuclear Power Plant, Östhammar 742 03, Sweden
Abstract
Abstract
The Moody and Henry–Fauske critical flow models implemented in Advanced Process Simulation Software (apros) have been validated against Marviken critical flow experiments and compared with other available simulations of the same experiments. Both models in combination with discharge coefficient 0.75 (suggested for best estimate calculations) produce results close to the experimental data for two-phase flows, while one-phase flow of subcooled water is underpredicted. Using discharge coefficient 1.0 for subcooled water leads to a good match with the experimental results, while two-phase flows become overpredicted.
Subject
Nuclear Energy and Engineering,Radiation
Reference22 articles.
1. Prediction of Two-Phase Choked-Flow Through Safety Valves;J. Phys.: Conf. Ser.,2014
2. Benchmark of Delayed Equilibrium Model (Dem) and Classic Two-Phase Critical Flow Models Against Experimental Data;Int. J. Multiphase Flow,2017
3. Critical Flow Maps Using an Extended Henry–Fauske Model;Ann. Nucl. Energy,2015
4. APROS Multifunctional Simulator for Thermal and Nuclear Power Plants,1997
5. Subcooled and Two Phase Critical Flow States and Comparison With Data;Nucl. Eng. Des.,1978
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1 articles.
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