Thermal–hydraulic evaluation of the RBMK-1500 accident confinement system using CONTAIN 11AF |
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Authors: | K. Almenas B. Cesna A. Kaliatka S Rimkevicius E. Uspuras E. Zvinys |
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Affiliation: | a Department of Nuclear Engineering, University of Maryland, College Park, MD 20742-2115, USA;b Lithuanian Energy Institute, Ignalina Safety Analyses Group, Breslaujos 3, LT-3035 Kaunas, Lithuania |
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Abstract: | The response of the RBMK Accident Confinement System to a large break LOCA, medium break LOCA and small break LOCA is analyzed using the CONTAIN 11AF code. The effect of Condenser Tray Cooling System failure is investigated for the large break LOCA case. The analysis employs a best estimate mass/energy source and considers both short and long-term responses of the Accident Confinement System. Parametric studies are performed to evaluate the effects of water deposition on the short-term pressure peak and of by-pass leakage on long-term pressure increases. |
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