Title: Thermal-hydraulic modeling of the primary coolant system of light water reactors during severely degraded core accidents
Abstract: A computer code has been developed to predict the time history of the primary coolant system (PCS) thermalhydraulics during severely degraded core accidents. The developed PCS code is modular and simulates both pressurized and boiling water reactor primary systems. The developed model assumes a one dimensional flow of steam and hydrogen along the PCS. The heat transfer between the gas and structures is by either forced or natural convection and radiation. Heterogeneous condensation on cold surfaces, accounting for the effects of noncondensables, is included. The calculations commence with core uncovery. The predicted PCS thermalhydraulic information includes flow parameters, such as, system pressure, flow rate and gas temperature within each component, temperature of the structures within each component along the flow path, heat and mass transfer coefficients, water levels where appropriate and other thermalhydraulic information which is required for aerosol tracking calculations.
Publication Year: 1984
Publication Date: 1984-07-01
Language: en
Type: article
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Cited By Count: 4
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