Evaluation of Sokrat Code Possibility to Model Uranium-Dioxide Fuel Dissolution by Molten Zirconium
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DOI: 10.1007/s10512-018-0446-x
Abstract: A quantitative assessment is made of the possibilities of the SOKRAT code to model the dissolution of uranium dioxide fuel by zirconium cladding melt at the initial stage of a serious accident at NPP with… read more here.
Keywords: dissolution; uranium dioxide; dioxide fuel; model ... See more keywords