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Norkus, J.K.; Corradini, M.L.
Electric Power Research Inst., Palo Alto, CA (United States); Wisconsin Univ., Madison, WI (United States). Dept. of Nuclear Engineering and Engineering Physics. Funding organisation: Electric Power Research Inst., Palo Alto, CA (United States)1991
Electric Power Research Inst., Palo Alto, CA (United States); Wisconsin Univ., Madison, WI (United States). Dept. of Nuclear Engineering and Engineering Physics. Funding organisation: Electric Power Research Inst., Palo Alto, CA (United States)1991
AbstractAbstract
[en] The study of molten core-concrete interaction is important in estimating the possible consequences of a severe nuclear reactor accident. CORCON-Mod2 is a computer program which models the thermal, chemical, and physical phenomena associated with molten core-concrete interactions. Models have been added to extend and improve the modeling of these phenomena. An ideal solution chemical equilibrium methodology is presented to predict the fission-product vaporization release. Additional chemical species have been added, and the calculation of chemical equilibrium has been expanded to the oxidic layer and to the mixed layer configuration. Recent experiments performed at Argonne National Laboratory are compared to CORCON predictions of melt temperature, erosion depth, and release fraction of fission products. The results consistently underpredicted the melt temperatures and erosion rates. However, the predictions of release of Te, Ba, Sr, and U were good. A sensitivity study of the effects of initial temperature, concrete type, use of the mixing option, degree of zirconium oxidation, cavity size, and amount of control material on erosion, gas production, and release of radioactive materials was performed for a PWR and a BWR. The initial melt temperature had the greatest effect on the results of interest. Concrete type and cavity size also had important effects. 78 refs., 35 figs., 40 tabs
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Sep 1991; 147 p; Research Reports Center, PO Box 50490, Palo Alto, CA 94303
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Report
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AEROSOLS, AFTER-HEAT, BWR TYPE REACTORS, C CODES, CARBON MONOXIDE, CHEMICAL REACTION KINETICS, CHEMICAL REACTIONS, CONCRETES, CORIUM, D CODES, EROSION, EVAPORATION, FISSION PRODUCT RELEASE, FISSION PRODUCTS, FLUID FLOW, HEAT TRANSFER, HYDRAULICS, HYDROGEN, M CODES, MATHEMATICAL MODELS, MELTDOWN, NUCLEAR POWER PLANTS, PWR TYPE REACTORS, REACTOR SAFETY, REACTOR VESSELS, SENSITIVITY ANALYSIS, SOURCE TERMS, VOID FRACTION
ACCIDENTS, BUILDING MATERIALS, CARBON COMPOUNDS, CARBON OXIDES, CHALCOGENIDES, COLLOIDS, COMPUTER CODES, CONTAINERS, DISPERSIONS, ELEMENTS, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, ISOTOPES, KINETICS, MATERIALS, NONMETALS, NUCLEAR FACILITIES, OXIDES, OXYGEN COMPOUNDS, PHASE TRANSFORMATIONS, POWER PLANTS, POWER REACTORS, RADIOACTIVE MATERIALS, REACTION KINETICS, REACTOR ACCIDENTS, REACTORS, SAFETY, SOLS, THERMAL POWER PLANTS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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