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- W295153241 abstract "In evaluating core debris/concrete interactions for a BWR MK I containment design, it has been common practice to assume that at reactor vessel breach, the core debris is homogeneous and of low viscosity so that it is uniformly distributed radially on the drywell floor. In a recent study performed by the NRC-sponsored Severe Accident Sequence Analysis (SASA) program at Oak Ridge National Laboratory, calculations indicate that at reactor vessel bottom head failure, the debris temperature is such that the metallic components (Zr, Fe, Ni, Cr) are completely molten while the oxidic components (UO/sub 2/, ZrO/sub 2/, FeO) are completely frozen. Thus, the frozen oxides are expected to remain within the reactor pedestal while the molten metallic species radially separate from the frozen oxidic species, flow through the opening in the reactor pedestal, and spread over the annular region of the drywell floor between the pedestal and the containment shell. This report assesses the impact on calculated debris gas release and the production and release of fission product-laden aerosols for two different cases of debris distribution: uniform distribution, and the laterally separated case of 95% oxides-5% metals inside the pedestal and 5% oxides-95% metals outside the pedestal. The computer codes usedmore » in this assessment are CORCON-MOD 2, MARCON 2.1B and VANESA.« less" @default.
- W295153241 created "2016-06-24" @default.
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- W295153241 date "1987-01-01" @default.
- W295153241 modified "2023-09-27" @default.
- W295153241 title "Effects of lateral separation of oxidic and metallic core debris on the BWR (Boiling Water Reactor) MK I containment drywell floor" @default.
- W295153241 hasPublicationYear "1987" @default.
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